bibliography.bib

@misc{bachmann_mmr-like_2023,
	title = {{MMR}-like {Serpent} {Model}},
	url = {https://zenodo.org/record/8349385},
	abstract = {A serpent model designed after the Ultra Safe Nuclear Corporation (USNC) Micro Modular Reactor (MMR) reactor design, based on publicly available information.},
	urldate = {2023-09-19},
	publisher = {Zenodo},
	author = {Bachmann},
	month = sep,
	year = {2023},
	doi = {10.5281/zenodo.8349385},
	keywords = {Monte Carlo, Microreactor},
	file = {Zenodo Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\GSCGL36K\\8349385.html:text/html},
}

@misc{bachmann_openmcyclus_2023,
	title = {{OpenMCyclus} v0.1.0},
	url = {https://zenodo.org/record/8349474},
	abstract = {Third party archetype for Cyclus to model a reactor facility that is coupled with the stand-alone depletion solver in OpenMC to dynamically update fuel compositions.},
	urldate = {2023-09-19},
	publisher = {Zenodo},
	author = {Bachmann, Amanda M. and Yardas, Olek and Munk, Madicken},
	month = sep,
	year = {2023},
	doi = {10.5281/zenodo.8349474},
	keywords = {depletion, nuclear fuel cycles},
	file = {Zenodo Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\7XQU7XEE\\8349474.html:text/html},
}

@article{vermeeren_development_2021,
	title = {Development of a {MOX} equivalence {Python} code package for {ANICCA}},
	volume = {7},
	issn = {2491-9292},
	url = {https://www.epj-n.org/10.1051/epjn/2021023},
	doi = {10.1051/epjn/2021023},
	abstract = {The basis of the MOX (Mixed OXide) energy equivalence principle is keeping the in-core fuel management characteristics (cycle length, feed size, etc.) of a nuclear reactor unchanged when replacing UOX (Uranium OXide) fuel assemblies by MOX. If the effect of the loading pattern is neglected, such an equivalence is obtained by tuning the Pu content in the MOX fuel, while considering the specific Pu isotopic vector at the time of the core reload to obtain a crossing of the reactivity curves of UOX and MOX at the end-of-cycle core average burnup. It is proposed in this work to extend the fuel cycle analysis tool ANICCA (Advanced Nuclear Inventory Cycle Code) with a MOX equivalence Python code package, which automatically governs the supply and demand of Pu vector isotopes required to obtain MOX equivalence. This code package can determine the reactivity evolution for any given Pu vector by means of a multidimensional interpolation on a directive grid of pre-calculated data tables generated by WIMS10, covering the physically accessible Pu vector space. A fuel cycle scenario will be assessed for a representative evolution of the Pu vector inventory available in spent UOX fuel as a demonstration case, defining the interim fuel storage building dimensional requirements for different reprocessing strategies.},
	urldate = {2023-09-13},
	journal = {EPJ Nuclear Sciences \& Technologies},
	author = {Vermeeren, Bart and Druenne, Hubert},
	editor = {Courtin, Fanny and Alvarez-Velarde, Francisco and Moisy, Philippe and Tillard, Léa},
	year = {2021},
	pages = {25},
}

@techreport{arm_plan_2022,
	title = {Plan for {Developing} {TRISO} {Fuel} {Processing} {Technologies}},
	url = {https://www.osti.gov/biblio/1874375},
	abstract = {This Plan demonstrates the availability of technologies for processing TRISO used nuclear fuel for waste management and actinide recovery purposes. These technologies are judged to be at a very low level of technology readiness and as such they constitute a fertile research area for the DOE-NE’s Office of Materials and Chemical Technologies. Strategies to mature the technologies to a point where they can reasonably be considered in engineering alternatives analyses typically involve laboratory-scale tests using fuel simulant to characterize process streams and demonstrate key engineering features. Several criteria are available to help selecting candidate technologies for further maturation},
	language = {English},
	number = {PNNL-32969},
	urldate = {2023-09-12},
	institution = {Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)},
	author = {Arm, Stuart T. and Hall, Gabriel B. and Lumetta, Gregg J. and Wells, Beric E.},
	month = jun,
	year = {2022},
	doi = {10.2172/1874375},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\STQWPTBE\\Arm et al. - 2022 - Plan for Developing TRISO Fuel Processing Technolo.pdf:application/pdf},
}

@misc{noauthor_higher_2023,
	title = {Higher {Burnup}},
	url = {https://www.nrc.gov/reactors/power/atf/technologies/burnup.html},
	language = {en-US},
	urldate = {2023-09-08},
	journal = {NRC Web},
	month = jul,
	year = {2023},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\WGLF8K8D\\burnup.html:text/html},
}

@phdthesis{sumner_effects_2011,
	title = {Effects of fuel type on the safety characteristics of a sodium-cooled fast reactor},
	url = {https://linkinghub.elsevier.com/retrieve/pii/S0306454911001010},
	language = {en},
	urldate = {2023-09-06},
	school = {Georgia Institute of Technology},
	author = {Sumner, Tyler},
	month = jul,
	year = {2011},
	file = {Sumner and Ghiaasiaan - 2011 - Effects of fuel type on the safety characteristics.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\ZU9H6N64\\Sumner and Ghiaasiaan - 2011 - Effects of fuel type on the safety characteristics.pdf:application/pdf},
}

@misc{noauthor_standard_2021,
	title = {Standard {Specification} for {Uranium} {Metal} {Enriched} to {Less} than 20\% {235U}},
	url = {https://compass.astm.org/document/?contentCode=ASTM%7CC1462-21%7Cen-US&proxycl=https%3A%2F%2Fsecure.astm.org&fromLogin=true},
	urldate = {2023-08-10},
	month = nov,
	year = {2021},
	file = {compass:C\:\\Users\\abachmann\\Zotero\\storage\\C2IZE7XC\\document.html:text/html},
}

@misc{noauthor_standard_2020,
	title = {Standard {Specification} for {Uranium} {Hexafluoride} {Enriched} to {Less} {Than} 5\% {235U}},
	url = {https://compass.astm.org/document/?contentCode=ASTM%7CC0996-20%7Cen-US&proxycl=https%3A%2F%2Fsecure.astm.org&fromLogin=true},
	urldate = {2023-08-10},
	month = apr,
	year = {2020},
	file = {compass:C\:\\Users\\abachmann\\Zotero\\storage\\NBK6GHMC\\document.html:text/html},
}

@misc{noauthor_standard_2022,
	title = {Standard {Specification} for {Sintered} {Uranium} {Dioxide} {Pellets} for {Light} {Water} {Reactors}},
	url = {https://compass.astm.org/document/?contentCode=ASTM%7CC0776-17R22%7Cen-US&proxycl=https%3A%2F%2Fsecure.astm.org&fromLogin=true},
	urldate = {2023-08-10},
	month = jul,
	year = {2022},
	file = {compass:C\:\\Users\\abachmann\\Zotero\\storage\\YXQDE3NG\\document.html:text/html},
}

@misc{noauthor_standard_2021-1,
	title = {Standard {Specification} for {Nuclear}-{Grade}, {Sinterable} {Uranium} {Dioxide} {Powder}},
	url = {https://compass.astm.org/document/?contentCode=ASTM%7CC0753-16AR21%7Cen-US&proxycl=https%3A%2F%2Fsecure.astm.org&fromLogin=true},
	urldate = {2023-08-10},
	month = oct,
	year = {2021},
	file = {compass:C\:\\Users\\abachmann\\Zotero\\storage\\PLDZ92IP\\document.html:text/html},
}

@article{noauthor_nureg-1368_1994,
	title = {{NUREG}-1368, "{Preapplication} {Safety} {Evaluation} {Report} for the {Power} {Reactor} {Innovative} {Small} {Module} ({PRISM}) {Liquid}-{Metal} {Reactor}."},
	language = {en},
	month = feb,
	year = {1994},
	file = {NUREG-1368, Preapplication Safety Evaluation Repo.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\8CC7V9HK\\NUREG-1368, Preapplication Safety Evaluation Repo.pdf:application/pdf},
}

@techreport{kim_pros_2023,
	title = {Pros and {Cons} {Analysis} of {HALEU} {Utilization} in {Example} {Fuel} {Cycles}},
	url = {https://fuelcycleoptions.inl.gov/SiteAssets/SitePages/Home/182926.pdf},
	number = {ANL/NSE-22/21},
	urldate = {2023-08-09},
	author = {Kim, TK and Hoffman, E and Dixon, B and Cuadra, A},
	month = jun,
	year = {2023},
	file = {182926.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\EAPRH5N6\\182926.pdf:application/pdf},
}

@article{fichtlscherer_assessing_2019,
	title = {Assessing the {PRISM} reactor as a disposition option for the {British} plutonium stockpile},
	volume = {27},
	issn = {0892-9882},
	url = {https://doi.org/10.1080/08929882.2019.1681736},
	doi = {10.1080/08929882.2019.1681736},
	abstract = {The United Kingdom considered using the PRISM sodium-cooled fast reactor as a disposition option for its civilian plutonium from reprocessed MAGNOX and Advanced Gas-cooled Reactor spent fuel. This article assesses the plutonium disposition capabilities of the PRISM reactor for the U.K. stockpile. The article first describes how the stockpile was created. It then provides a simulation of reactor burn-up, the resultant isotopic compositions of PRISM spent fuel are simulated and the dose rates of that fuel. Dose rates greater than 1 Sv/h at 1 meter from the fuel were assumed to establish “proliferation resistance” and would constitute a radiation barrier to proliferators. Results suggest that the U.K. stockpile could be irradiated to that proliferation resistance target in 31.3 years, using two 840 MWth PRISM cores operating at a 30 MWd/kgHM burnup rate. By the time all the U.K. plutonium has been irradiated, however a fraction of the PRISM spent fuel will have decayed below the proliferation resistance target. Thus, even though in 2019 PRISM was removed from consideration by the U.K. government because it is not expected to be available for that use for another 20 years, this paper concludes that should PRISM become available earlier it would still be a poor choice for plutonium disposition.},
	number = {2-3},
	urldate = {2023-08-02},
	journal = {Science \& Global Security},
	author = {Fichtlscherer, Christopher and Frieß, Friederike and Kütt, Moritz},
	month = sep,
	year = {2019},
	note = {Publisher: Routledge
\_eprint: https://doi.org/10.1080/08929882.2019.1681736},
	pages = {124--149},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\7GDF3GWU\\Fichtlscherer et al. - 2019 - Assessing the PRISM reactor as a disposition optio.pdf:application/pdf},
}

@article{kuijper_htgr_2006,
	title = {{HTGR} reactor physics and fuel cycle studies},
	volume = {236},
	issn = {00295493},
	url = {https://linkinghub.elsevier.com/retrieve/pii/S0029549306000161},
	doi = {10.1016/j.nucengdes.2005.10.021},
	abstract = {The high-temperature gas-cooled reactor (HTGR) appears as a good candidate for the next generation of nuclear power plants. In the “HTR-N” project of the European Union Fifth Framework Program, analyses have been performed on a number of conceptual HTGR designs, derived from reference pebble-bed and hexagonal block-type HTGR types. It is shown that several HTGR concepts are quite promising as systems for the incineration of plutonium and possibly minor actinides.},
	language = {en},
	number = {5-6},
	urldate = {2023-07-31},
	journal = {Nuclear Engineering and Design},
	author = {Kuijper, J.C. and Raepsaet, X. and De Haas, J.B.M. and Von Lensa, W. and Ohlig, U. and Ruetten, H.-J. and Brockmann, H. and Damian, F. and Dolci, F. and Bernnat, W. and Oppe, J. and Kloosterman, J.L. and Cerullo, N. and Lomonaco, G. and Negrini, A. and Magill, J. and Seiler, R.},
	month = mar,
	year = {2006},
	pages = {615--634},
	file = {Kuijper et al. - 2006 - HTGR reactor physics and fuel cycle studies.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\WKGPRQ7V\\Kuijper et al. - 2006 - HTGR reactor physics and fuel cycle studies.pdf:application/pdf},
}

@article{fukaya_proposal_2014,
	title = {Proposal of a plutonium burner system based on {HTGR} with high proliferation resistance},
	volume = {51},
	issn = {0022-3131},
	url = {https://doi.org/10.1080/00223131.2014.905803},
	doi = {10.1080/00223131.2014.905803},
	abstract = {An innovative plutonium burner concept based on high temperature gas cooled reactor (HTGR) technology, “Clean Burn”, is proposed by Japan Atomic Energy Agency (JAEA). That is expected to be as an effective and safe method to consume surplus plutonium accumulated in Japan. A similar concept proposed by General Atomics (GA), Deep Burn, cannot be introduced to Japan because of its adopting highly enriched plutonium, which shall infringe on a Japanese nuclear nonproliferation policy according to Japan–US reprocessing negotiation. The Clean Burn concept can avoid this problem by employing an inert matrix fuel (IMF) and a tightly coupled fuel reprocessing and fabrication plants. Both features make it impossible to extract plutonium alone out of the fabrication process and its outcomes. As a result, the Clean Burn can use surplus plutonium as a fuel without mixing it with uranium matrix. Thus, surplus plutonium alone will be incinerated effectively, while generation of plutonium from the uranium matrix is avoided. High neutronic performance, i.e., achievement of burn-up of about 500 GWd/t and consumption ratio of plutonium-239 reaching to about 95\%, is also assessed. Furthermore, reactivity defect caused by the inert matrix is found to be negligible. It is concluded that the Clean Burn concept is a useful option to incinerate plutonium with high proliferation resistance.},
	number = {6},
	urldate = {2023-07-31},
	journal = {Journal of Nuclear Science and Technology},
	author = {Fukaya, Yuji and Goto, Minoru and Ohashi, Hirofumi and Tachibana, Yukio and Kunitomi, Kazuhiko and Chiba, Satoshi},
	month = jun,
	year = {2014},
	note = {Publisher: Taylor \& Francis
\_eprint: https://doi.org/10.1080/00223131.2014.905803},
	keywords = {Clean Burn, Deep Burn, IMF, inert matrix fuel, plutonium burner reactor, proliferation resistance},
	pages = {818--831},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\96FEXGAC\\Fukaya et al. - 2014 - Proposal of a plutonium burner system based on HTG.pdf:application/pdf},
}

@misc{noauthor_modeling_nodate,
	title = {Modeling a {Pin}-{Cell}},
	url = {https://nbviewer.org/github/openmc-dev/openmc-notebooks/blob/main/pincell.ipynb},
	urldate = {2023-07-20},
	file = {Jupyter Notebook Viewer:C\:\\Users\\abachmann\\Zotero\\storage\\SDH9SUI9\\pincell.html:text/html},
}

@article{carbajo_review_2001,
	title = {A review of the thermophysical properties of {MOX} and {UO2} fuels},
	volume = {299},
	issn = {0022-3115},
	url = {https://www.sciencedirect.com/science/article/pii/S0022311501006924},
	doi = {10.1016/S0022-3115(01)00692-4},
	abstract = {A critical review of the thermophysical properties of UO2 and MOX fuels has been completed, and the best correlations for thermophysical properties have been selected. The properties reviewed are solidus and liquidus temperatures of the uranium/plutonium dioxide system (melting and solidification temperatures), thermal expansion and density, enthalpy and specific heat, enthalpy (or heat) of fusion, and thermal conductivity. Only fuel properties have been reviewed. The selected set of property correlations was compiled to be used in thermal-hydraulic codes to perform safety calculations.},
	language = {en},
	number = {3},
	urldate = {2023-06-26},
	journal = {Journal of Nuclear Materials},
	author = {Carbajo, Juan J and Yoder, Gradyon L and Popov, Sergey G and Ivanov, Victor K},
	month = dec,
	year = {2001},
	pages = {181--198},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\TA6BZTL4\\Carbajo et al. - 2001 - A review of the thermophysical properties of MOX a.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\Z3JCEKWS\\S0022311501006924.html:text/html},
}

@misc{bae_jbae11ann_pwr_2019,
	title = {jbae11/ann\_pwr: {Zenodo} {Release}},
	shorttitle = {jbae11/ann\_pwr},
	url = {https://zenodo.org/record/3353745},
	abstract = {Cyclus batch-wise reactor module using neural network depletion model},
	urldate = {2023-06-22},
	publisher = {Zenodo},
	author = {Bae, Jin Whan},
	month = jul,
	year = {2019},
	doi = {10.5281/zenodo.3353745},
	file = {Zenodo Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\P5DUWA74\\3353745.html:text/html},
}

@article{leniau_neural_2015,
	title = {A neural network approach for burn-up calculation and its application to the dynamic fuel cycle code {CLASS}},
	volume = {81},
	issn = {0306-4549},
	url = {https://www.sciencedirect.com/science/article/pii/S0306454915001693},
	doi = {10.1016/j.anucene.2015.03.035},
	abstract = {Dynamic fuel cycle simulation tools calculate nuclei inventories and mass flows evolution in an entire fuel cycle, from the mine to the final disposal. Usually, the fuel depletion in reactor is handled by a fuel loading model and a mean cross section predictor. In the case of a PWR–MOX, a fuel loading model provides from a plutonium stock the plutonium fraction in the fresh fuel needed to reach a specific burnup. A mean cross section predictor aims to assess isotopic cross sections required for building Bateman equations for any fresh fuel composition with a sufficient accuracy and a reasonable computing time. This paper presents a methodology based on neural networks for building a fuel loading model and a cross section predictor for a PWR reactor loaded with MOX fuel. The mean error of the plutonium content prediction from the fuel loading model is 0.37\%. Furthermore, the mean cross section predictor allows completion of the fuel depletion calculation in less than one minute with excellent accuracy. A maximum deviation of 3\% on main nuclei is obtained at the end of cycle between inventories calculated from neural networks and from the reference coupled neutron transport/fuel depletion calculation.},
	language = {en},
	urldate = {2023-06-22},
	journal = {Annals of Nuclear Energy},
	author = {Leniau, Baptiste and Mouginot, Baptiste and Thiolliere, Nicolas and Doligez, Xavier and Bidaud, Adrien and Courtin, Fanny and Ernoult, Marc and David, Sylvain},
	month = jul,
	year = {2015},
	keywords = {Cross section predictor, MOX, Neural network, Nuclear scenario, PWR},
	pages = {125--133},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\F65WVPU9\\Leniau et al. - 2015 - A neural network approach for burn-up calculation .pdf:application/pdf},
}

@article{mulder_neutronics_2020,
	title = {Neutronics characteristics of a 165 {MWth} {Xe}-100 reactor},
	volume = {357},
	issn = {0029-5493},
	url = {https://www.sciencedirect.com/science/article/pii/S0029549319304467},
	doi = {10.1016/j.nucengdes.2019.110415},
	abstract = {The Xe-100 is a high temperature, helium-cooled, graphite moderated, pebble bed reactor (HTGR) featuring a 6-times through, multi-pass (MEDUL = MEhrfachDUrchLauf) fuelling scheme. It is designed for delivering heat in the form of superheated steam at 565 °C and 16.5 MPa. This steam can be used to generate electricity, provide process heat for petrochemical application, or for cogeneration applications, such as the treatment of contaminated water resources, whilst simultaneously generating electricity. The design is characterized as a Generation IV reactor, with a core that cannot melt and featuring safety characteristics that will eliminate the need at any time to evacuate or displace the public, or that will cause unallowable contamination of the land. The technology is based on proven technology that has demonstrated these safety claims both experimentally and in commercial deployment. The foundation of proof ensures high levels of design and technical readiness. In the overview presented below a parametric comparison is offered of a 165 MWth design against that of X-energy’s 200 MWth reference Xe-100 design. The excess reactivity in both cases is shown to be limited by the continuous fuelling regime, whilst the core geometry and selected core power density enables passive heat removal. In this way the desired intrinsic safety design features of a typical GEN IV design are guaranteed. It is shown that even in the event of a depressurized loss of forced coolant (DLOFC) design basis event, no significant amount of radiological material will be released. A larger margin of tolerance is afforded in the 165 MWth design case, as expected. The coupled core neutronic and thermo-fluid dynamics design for the Xe-100 is performed with the VSOP-A and MGT systems of codes. For the equilibrium core, VSOP results demonstrate that the spherical fuel powers (maximum 3.0 kW) and operational temperatures ({\textless}1000 °C) fall well within the envelope of the design criteria. Adequate reactivity control and long-term, cold shutdown are provided by two separate, independently actuated systems, while the overall negative reactivity temperature coefficient is illustrated over the total operational range.},
	language = {en},
	urldate = {2022-09-26},
	journal = {Nuclear Engineering and Design},
	author = {Mulder, E. J. and Boyes, W. A.},
	month = feb,
	year = {2020},
	keywords = {TRISO, HTGR, MEDUL, MGT, Pebble bed reactor, VSOP-A, Xe-100},
	pages = {110415},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\Z2LV7SCV\\Mulder and Boyes - 2020 - Neutronics characteristics of a 165 MWth Xe-100 re.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\CGHU4LEK\\S0029549319304467.html:text/html},
}

@article{schneider_nfcsim:_2005,
	title = {{NFCSim}: {A} {Dynamic} {Fuel} {Burnup} and {Fuel} {Cycle} {Simulation} {Tool}},
	volume = {151},
	number = {1},
	journal = {Nuclear Technology},
	author = {Schneider, Erich A. and Bathke, Charles G. and James, Michael R.},
	month = jul,
	year = {2005},
	keywords = {Fuel cycle, Reactivity Modeling, Simulation},
	pages = {35--50},
	file = {NT-151-1-35-Schneider, et al.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\FV66APMP\\NT-151-1-35-Schneider, et al.pdf:application/pdf},
}

@article{jacobson_vision_2007,
	title = {{VISION} 2: {Enhanced} simulation model of the next generation nuclear fuel cycle},
	volume = {96},
	shorttitle = {{VISION} 2},
	journal = {Transactions of the American Nuclear Society},
	author = {JACOBSON, J. and YACOUT, A. and MATTHEM, G. and PIET, S. and SHROPSHIRE, D. and LAWS, C.},
	year = {2007},
	pages = {199--200},
	file = {Google Scholar Linked Page:C\:\\Users\\abachmann\\Zotero\\storage\\QFHJVFQB\\cat.inist.fr.html:text/html},
}

@article{li_sensitivity_2010,
	title = {The sensitivity of fuel cycle performance to separation efficiency},
	volume = {240},
	url = {http://www.sciencedirect.com/science/article/pii/S0029549309000843},
	number = {3},
	urldate = {2013-06-07},
	journal = {Nuclear Engineering and Design},
	author = {Li, Jun and Scopatz, Anthony and Yim, Man-Sung and Schneider, Erich},
	year = {2010},
	pages = {511--523},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\X9SNBIFU\\S0029549309000843.html:text/html},
}

@article{kim_development_2013,
	title = {Development and {Validation} of a {Nuclear} {Fuel} {Cycle} {Analysis} {Tool}: a {FUTURE} {Code}},
	volume = {45},
	url = {http://www.sciencedirect.com/science/article/pii/S1738573315300516},
	abstract = {This paper presents the development and validation methods of the FUTURE (FUel cycle analysis Tool for nUcleaR Energy) code, which was developed for a dynamic material flow evaluation and economic analysis of the nuclear fuel cycle. This code enables an evaluation of a nuclear material flow and its economy for diverse nuclear fuel cycles based on a predictable scenario. The most notable virtue of this FUTURE code, which was developed using C\# and MICROSOFT SQL DBMS, is that a program user can design a nuclear fuel cycle process easily using a standard process on the canvas screen through a drag-and-drop method. From the user’s point of view, this code is very easy to use thanks to its high flexibility. In addition, the new code also enables the maintenance of data integrity by constructing a database environment of the results of the nuclear fuel cycle analyses.},
	number = {5},
	journal = {Nuclear Engineering and Technology},
	author = {Kim, S.K. and Ko, W.I. and Lee, Y.H.},
	month = oct,
	year = {2013},
	pages = {665--674},
	file = {1-s2.0-S1738573315300516-main.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\VRE9BNCU\\1-s2.0-S1738573315300516-main.pdf:application/pdf},
}

@article{mouginot_class_2012,
	title = {{CLASS}, a new tool for nuclear scenarios: {Description} \& {First} {Application}},
	volume = {6},
	shorttitle = {{CLASS}, a new tool for nuclear scenarios},
	url = {http://citeseerx.ist.psu.edu/viewdoc/download?doi=10.1.1.222.5389&rep=rep1&type=pdf},
	number = {3},
	urldate = {2017-05-30},
	journal = {World Academy of Science, Engineering and Technology, International Journal of Mathematical, Computational, Physical, Electrical and Computer Engineering},
	author = {Mouginot, B. and Clavel, J. B. and Thiolliere, N.},
	year = {2012},
	pages = {232--235},
	file = {[PDF] psu.edu:C\:\\Users\\abachmann\\Zotero\\storage\\ZKJEBPFZ\\Mouginot et al. - 2012 - CLASS, a new tool for nuclear scenarios Descripti.pdf:application/pdf},
}

@article{wilson_comparing_2011,
	title = {Comparing {Nuclear} {Fuel} {Cycle} {Options}},
	url = {http://brc.gov/sites/default/files/documents/wilson.fuel_.cycle_.comparisons_final.pdf},
	journal = {A report for the Reactor \& Fuel Cycle Technology Subcommittee of the Blue Ribbon Commission on America's Nuclear Future},
	author = {Wilson, Paul P. H.},
	month = mar,
	year = {2011},
}

@inproceedings{durpel_daness_2003,
	address = {New Orleans, LA, United States},
	title = {Daness dynamic analysis of nuclear system strategies},
	isbn = {0-89448-677-2},
	abstract = {The dynamic analysis of multiple development paths for nuclear energy systems has gained interest worldwide. Especially in the light of the different roadmap exercises that have been undertaken in the past years indicating the need for symbiotic nuclear energy systems in the longer term. The symbiosis between different nuclear reactor types and their associated fuel cycle should fulfill competing objectives for such systems, i.e. economics, environmental friendliness, resource longevity, waste management, and non-proliferation. A new code, dubbed DANESS, has been developed which allows performing such dynamic analysis of nuclear energy systems composed of multiple reactors and fuel cycle options including cross-flow of fissile material between the different components of the system. Today, the code allows mass-flow analysis and economics and is currently being extended to include life-cycle analysis data, non-proliferation metrics and non-nuclear energy sources. This paper will describe the main features of this code and will indicate the possible uses and future developments.},
	booktitle = {Global 2003: {Atoms} for {Prosperity}: {Updating} {Eisenhouwer}'s {Global} {Vision} for {Nuclear} {Energy}},
	publisher = {American Nuclear Society},
	author = {Durpel, L. Van Den and Yacout, A. and Wade, D. and Khalil, H.},
	month = nov,
	year = {2003},
	note = {Compilation and indexing terms, Copyright 2006 Elsevier Inc. All rights reserved; T3: Global 2003: Atoms for Prosperity: Updating Eisenhouwer's Global Vision for Nuclear Energy},
	keywords = {Fuels, Management, Energy, Technology, Light Water Reactors (LWR), Development, Environmental Impact, Reduction, nuclear, Data, Fast, Research, Transfer, Waste},
	pages = {1613--1620},
	file = {1613.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\Q854B4VR\\1613.pdf:application/pdf},
}

@article{jacobson_vision:_2006,
	title = {{VISION}: {Verifiable} fuel cycle simulation model},
	volume = {95},
	shorttitle = {{VISION}},
	url = {http://www.inl.gov/technicalpublications/Documents/4215160.pdf},
	journal = {TRANSACTIONS-AMERICAN NUCLEAR SOCIETY},
	author = {Jacobson, J. and Yacout, A. M and Matthern, G. and Piet, S. and Shropshire, D. E and Laws, C.},
	year = {2006},
	pages = {157},
	file = {Google Scholar Linked Page:C\:\\Users\\abachmann\\Zotero\\storage\\G6SVH5CF\\Jacobson et al. - 2006 - VISION Verifiable fuel cycle simulation model.pdf:application/pdf},
}

@article{piet_which_2007,
	title = {Which {Elements} {Should} {Be} {Recycled} for a {Comprehensive} {Fuel} {Cycle}?},
	volume = {1595},
	journal = {Proc. Global 2007},
	author = {Piet, S. and Bjornard, T. and Dixon, B. and Gombert, D. and Laws, C. and Matthern, G.},
	year = {2007},
	file = {Google Scholar Linked Page:C\:\\Users\\abachmann\\Zotero\\storage\\SGB34CGP\\Piet et al. - 2007 - Which Elements Should Be Recycled for a Comprehens.pdf:application/pdf},
}

@article{yue_fuel_2018,
	title = {Fuel cycles optimization of nuclear power industry in {China}},
	volume = {111},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454917303262},
	doi = {10.1016/j.anucene.2017.09.049},
	abstract = {With the rapid rise of installed nuclear power in China, meeting the increasing demands on natural uranium and rationally treating the vast spent fuel are essential issues for the sustainable development of Chinese nuclear power industry. This paper discusses four most potential nuclear fuel cycle modes in China and analyzes the natural uranium requirements under these different fuel cycle modes first based on three development patterns (low-, medium-, and high-speed) of installed nuclear power capacity. Then, an optimization model including natural uranium requirements, spent fuel final disposal amounts and total cost of electricity generation is constructed and optimization problem under two scenarios of reprocessing capacity are solved and results discussed. The annual and cumulative natural uranium requirements under these two scenarios are also calculated. Finally some conclusions are put forward based on the analyses.},
	number = {Supplement C},
	urldate = {2017-12-11},
	journal = {Annals of Nuclear Energy},
	author = {Yue, Qiang and He, Jingke and Zhi, Shengke and Dong, Hui},
	month = jan,
	year = {2018},
	keywords = {Spent fuel, Fuel cycle, Optimization, Cost, Natural uranium, Nuclear power industry},
	pages = {635--643},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\VA9H45SL\\Yue et al. - 2018 - Fuel cycles optimization of nuclear power industry.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\F9KQTVXF\\S0306454917303262.html:text/html},
}

@inproceedings{yacout_vision_2006,
	title = {{VISION} -- {Verifiable} {Fuel} {Cycle} {Simulation} of {Nuclear} {Fuel} {Cycle} {Dynamics}},
	url = {http://www.inl.gov/technicalpublications/Documents/3394908.pdf},
	booktitle = {Waste {Management} {Symposium}},
	author = {Yacout, A. M. and Jacobson, J. J. and Matthern, G. E. and Piet, S. J. and Shropshire, D. E. and Laws, C.},
	year = {2006},
	file = {Google Scholar Linked Page:C\:\\Users\\abachmann\\Zotero\\storage\\P3TPNT3H\\Yacout et al. - 2006 - VISION–Verifiable Fuel Cycle Simulation of Nuclear.pdf:application/pdf},
}

@article{freynet_multiobjective_2016,
	title = {Multiobjective optimization for nuclear fleet evolution scenarios using {COSI}},
	volume = {2},
	url = {http://epjn.epj.org/articles/epjn/abs/2016/01/epjn150066/epjn150066.html},
	urldate = {2017-02-17},
	journal = {EPJ Nuclear Sciences \& Technologies},
	author = {Freynet, David and Coquelet-Pascal, Christine and Eschbach, Romain and Krivtchik, Guillaume and Merle-Lucotte, Elsa},
	year = {2016},
	pages = {9},
	file = {[HTML] epj-n.org:C\:\\Users\\abachmann\\Zotero\\storage\\AVP329PE\\epjn150066.html:text/html;[HTML] epj-n.org:C\:\\Users\\abachmann\\Zotero\\storage\\ZHNXV2WH\\epjn150066.html:text/html;epjn150066.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\HA6HH8VJ\\epjn150066.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\HIBGZJTC\\epjn150066.html:text/html;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\8URTHTBQ\\epjn150066.html:text/html},
}

@techreport{peterson_used_2013,
	title = {Used {Nuclear} {Fuel} {Storage} {Transportation} \& {Disposal} {Analysis} {Resource} and {Data} {System} ({UNF}-{ST}\&{DARDS})},
	institution = {FCRD-NFST-2013-000117 Rev. 0, US Department of Energy Nuclear Fuels Storage and Transportation Planning Project},
	author = {Peterson, J. and Lefebvre, R. and Smith, H. and Ilas, D. and Robb, K. and Michener, T. and Adkins, H. and Scaglione, J.},
	year = {2013},
}

@article{kim_selection_1999,
	title = {Selection of an optimal nuclear fuel cycle scenario by goal programming and the analytic hierarchy process},
	volume = {26},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454998000814},
	doi = {10.1016/S0306-4549(98)00081-4},
	abstract = {The front-end fuel cycle from mining to enrichment has reached maturity. Unlike the front-end fuel cycle, there are several pathways in the back-end fuel cycle. The long-term consequences of any decision for the back-end fuel cycle requires some sophisticated decision making tools. Various kinds of factors should be taken into consideration for the decision. In this study the Goal Programming Method in combination with the Analytic Hierarchy Process (AHP) is applied in the decision making process. For the treatment of tangible factors Goal Programming is used and for intangible factors AHP is used for quantification. A computer code was developed to combine both methods in the treatment of two different kinds of factors and to obtain a solution for the most optimal fuel cycle in Korea.},
	number = {5},
	urldate = {2017-10-15},
	journal = {Annals of Nuclear Energy},
	author = {Kim, Poong Oh and Lee, Kun Jai and Lee, Byong Whi},
	month = mar,
	year = {1999},
	pages = {449--460},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\SA6P2782\\Kim et al. - 1999 - Selection of an optimal nuclear fuel cycle scenari.pdf:application/pdf;ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\BFI8GQB5\\Kim et al. - 1999 - Selection of an optimal nuclear fuel cycle scenari.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\JS36TCCQ\\S0306454998000814.html:text/html;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\DE6792DP\\S0306454998000814.html:text/html},
}

@article{brinton_nuclear_2013,
	title = {A nuclear fuel cycle system dynamic model for spent fuel storage options},
	issn = {0196-8904},
	url = {http://www.sciencedirect.com/science/article/pii/S0196890413001854},
	doi = {10.1016/j.enconman.2013.03.041},
	abstract = {Abstract 
The options for used nuclear fuel storage location and affected parameters such as economic liabilities are currently a focus of several high level studies. A variety of nuclear fuel cycle system analysis models are available for such a task. The application of nuclear fuel cycle system dynamics models for waste management options is important to life-cycle impact assessment. 
 
The recommendations of the Blue Ribbon Committee on America’s Nuclear Future led to increased focus on long periods of spent fuel storage [1]. This motivated further investigation of the location dependency of used nuclear fuel in the parameters of economics, environmental impact, and proliferation risk. 
 
Through a review of available literature and interactions with each of the programs available, comparisons of post-reactor fuel storage and handling options will be evaluated based on the aforementioned parameters and a consensus of preferred system metrics and boundary conditions will be provided. Specifically, three options of local, regional, and national storage were studied. The preliminary product of this research is the creation of a system dynamics tool known as the Waste Management Module (WMM) which provides an easy to use interface for education on fuel cycle waste management economic impacts. Initial results of baseline cases point to positive benefits of regional storage locations with local regional storage options continuing to offer the lowest cost.},
	urldate = {2013-05-28},
	journal = {Energy Conversion and Management},
	author = {Brinton, Samuel and Kazimi, Mujid},
	year = {2013},
	keywords = {Used nuclear fuel, Waste management, Systems analysis},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\3WAQG7MG\\Brinton and Kazimi - A nuclear fuel cycle system dynamic model for spen.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\97DF2IC2\\S0196890413001854.html:text/html;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\NZHA4E53\\Brinton and Kazimi - A nuclear fuel cycle system dynamic model for spen.html:text/html},
}

@article{worrall_utilization_2013,
	title = {Utilization of used nuclear fuel in a potential future {US} fuel cycle scenario},
	journal = {WM2013, Phoenix, AZ},
	author = {Worrall, Andrew},
	year = {2013},
	file = {Fulltext:C\:\\Users\\abachmann\\Zotero\\storage\\FUQ7LMIK\\Worrall - 2013 - Utilization of used nuclear fuel in a potential fu.pdf:application/pdf;Pub40177.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\RZQWHNCY\\Pub40177.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\J9BHZM8B\\Worrall - 2013 - Utilization of used nuclear fuel in a potential fu.pdf:application/pdf},
}

@article{andrianov_optimization_2019,
	title = {Optimization models of a two-component nuclear energy system with thermal and fast reactors in a closed nuclear fuel cycle},
	volume = {5(1)},
	copyright = {2019Andrey A. Andrianov, Ilya S. Kuptsov, Tatyana A. Osipova, Olga N. Andrianova, Tatyana V. Utyanskaya},
	issn = {2452-3038},
	url = {https://nucet.pensoft.net/article/33981/},
	doi = {10.3897/nucet.5.33981},
	abstract = {The article presents a description and some illustrative results of the application of two optimization models for a two-component nuclear energy system consisting of thermal and fast reactors in a closed nuclear fuel cycle. These models correspond to two possible options of developing Russian nuclear energy system, which are discussed in the expert community: (1) thermal and fast reactors utilizing uranium and mixed oxide fuel, (2) thermal reactors utilizing uranium oxide fuel and fast reactors utilizing mixed nitride uranium-plutonium fuel. The optimization models elaborated using the IAEA MESSAGE energy planning tool make it possible not only to optimize the nuclear energy system structure according to the economic criterion, taking into account resource and infrastructural constraints, but also to be used as a basis for developing multi-objective, stochastic and robust optimization models of a two-component nuclear energy system. These models were elaborated in full compliance with the recommendations of the IAEA’s PESS and INPRO sections, regarding the specification of nuclear energy systems in MESSAGE. The study is based on publications of experts from NRC “Kurchatov Institute”, JSC “SSC RF-IPPE”, ITCP “Proryv”, JSC “NIKIET”. The presented results demonstrate the characteristic structural features of a two-component nuclear energy system for conservative assumptions in order to illustrate the capabilities of the developed optimization models. Consideration is also given to the economic feasibility of a technologically diversified nuclear energy structure providing the possibility of forming on its base a robust system in the future. It has been demonstrated that given the current uncertainties in the costs of nuclear fuel cycle services and reactor technologies, it is impossible at the moment to make a reasonable conclusion regarding the greatest attractiveness of a particular option in terms of the economic performance.},
	language = {en},
	urldate = {2019-03-26},
	journal = {Nuclear Energy and Technology},
	author = {Andrianov, Andrey A. and Kuptsov, Ilya S. and Osipova, Tatyana A. and Andrianova, Olga N. and Utyanskaya, Tatyana V.},
	month = mar,
	year = {2019},
	pages = {39--45},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\WWTLB57J\\WWTLB57J.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\AQ32RZAI\\articles.html:text/html},
}

@article{romano_openmc:_2015,
	series = {Joint {International} {Conference} on {Supercomputing} in {Nuclear} {Applications} and {Monte} {Carlo} 2013, {SNA} + {MC} 2013. {Pluri}- and {Trans}-disciplinarity, {Towards} {New} {Modeling} and {Numerical} {Simulation} {Paradigms}},
	title = {{OpenMC}: {A} state-of-the-art {Monte} {Carlo} code for research and development},
	volume = {82},
	issn = {0306-4549},
	shorttitle = {{OpenMC}},
	url = {http://www.sciencedirect.com/science/article/pii/S030645491400379X},
	doi = {10.1016/j.anucene.2014.07.048},
	abstract = {This paper gives an overview of OpenMC, an open source Monte Carlo particle transport code recently developed at the Massachusetts Institute of Technology. OpenMC uses continuous-energy cross sections and a constructive solid geometry representation, enabling high-fidelity modeling of nuclear reactors and other systems. Modern, portable input/output file formats are used in OpenMC: XML for input, and HDF5 for output. High performance parallel algorithms in OpenMC have demonstrated near-linear scaling to over 100,000 processors on modern supercomputers. Other topics discussed in this paper include plotting, CMFD acceleration, variance reduction, eigenvalue calculations, and software development processes.},
	number = {Supplement C},
	urldate = {2017-11-22},
	journal = {Annals of Nuclear Energy},
	author = {Romano, Paul K. and Horelik, Nicholas E. and Herman, Bryan R. and Nelson, Adam G. and Forget, Benoit and Smith, Kord},
	month = aug,
	year = {2015},
	keywords = {HDF5, Monte Carlo, Neutron transport, OpenMC, Parallel, XML},
	pages = {90--97},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\9S36DPTN\\Romano et al. - 2015 - OpenMC A state-of-the-art Monte Carlo code for re.pdf:application/pdf;ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\IW54R5QX\\Romano et al. - 2015 - OpenMC A state-of-the-art Monte Carlo code for re.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\NZ4279HS\\S030645491400379X.html:text/html;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\ALT6V9G9\\S030645491400379X.html:text/html},
}

@article{coquelet-pascal_cosi6:_2015,
	title = {{COSI6}: {A} {Tool} for {Nuclear} {Transition} {Scenario} {Studies} and {Application} to {SFR} {Deployment} {Scenarios} with {Minor} {Actinide} {Transmutation}},
	volume = {192},
	issn = {0029-5450, 1943-7471},
	shorttitle = {{COSI6}},
	url = {https://www.tandfonline.com/doi/full/10.13182/NT15-20},
	doi = {10.13182/NT15-20},
	language = {en},
	number = {2},
	urldate = {2019-07-07},
	journal = {Nuclear Technology},
	author = {Coquelet-Pascal, C. and Tiphine, M. and Krivtchik, G. and Freynet, D. and Cany, C. and Eschbach, R. and Chabert, C.},
	month = nov,
	year = {2015},
	pages = {91--110},
	file = {Coquelet-Pascal et al. - 2015 - COSI6 A Tool for Nuclear Transition Scenario Stud.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\64YP6ZEL\\Coquelet-Pascal et al. - 2015 - COSI6 A Tool for Nuclear Transition Scenario Stud.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\6ICA6XUV\\a_37671.html:text/html},
}

@techreport{amir_afzali_high_2018,
	title = {High {Temperature}, {Gas}-{Cooled} {Pebble} {Bed} {Reactor} licensing {Modernization} {Project} {Demonstration}},
	url = {https://www.nrc.gov/docs/ML1822/ML18228A779.pdf},
	number = {SC-29980-200 Rev 0},
	urldate = {2019-10-10},
	institution = {Southern Company},
	author = {{Amir Afzali}},
	month = aug,
	year = {2018},
	note = {U.S. Department of Energy (DOE)
Office of Nuclear Energy
Under DOE Idaho Operations Office
Contract DE-AC07-0SID14517},
	file = {ML18228A779.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\UUQZ8CCP\\ML18228A779.pdf:application/pdf},
}

@article{leppanen_serpent_2013,
	title = {Serpent -- a {Continuous}-energy {Monte} {Carlo} {Reactor} {Physics} {Burnup} {Calculation} {Code}},
	volume = {4},
	urldate = {2013-05-30},
	journal = {VTT Technical Research Centre of Finland, Espoo, Finland},
	author = {Leppanen, Jaakko},
	year = {2013},
	file = {[PDF] from vtt.fi:C\:\\Users\\abachmann\\Zotero\\storage\\4XX8BJFI\\Leppänen - 2012 - Serpent–a Continuous-energy Monte Carlo Reactor Ph.pdf:application/pdf;Fulltext:C\:\\Users\\abachmann\\Zotero\\storage\\4PZH3QLK\\Leppänen - 2013 - Serpent–a continuous-energy Monte Carlo reactor ph.pdf:application/pdf;Fulltext:C\:\\Users\\abachmann\\Zotero\\storage\\EERPAHXD\\Leppänen - 2013 - Serpent–a continuous-energy Monte Carlo reactor ph.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\JRNZXHIQ\\Leppänen - 2013 - Serpent–a continuous-energy Monte Carlo reactor ph.pdf:application/pdf},
}

@techreport{schneider_integrated_2016,
	title = {An {Integrated} {Fuel} {Depletion} {Calculator} for {Fuel} {Cycle} {Options} {Analysis}},
	url = {http://www.osti.gov/servlets/purl/1258475/},
	language = {en},
	number = {12-4065, 1258475},
	urldate = {2019-12-03},
	institution = {battelle Energy Alliance, LLC},
	author = {Schneider, Erich and Scopatz, Anthony},
	month = apr,
	year = {2016},
	doi = {10.2172/1258475},
	pages = {12--4065, 1258475},
	file = {[PDF] inl.gov:C\:\\Users\\abachmann\\Zotero\\storage\\7F44GAQ6\\Schneider and Scopatz - 2016 - An Integrated Fuel Depletion Calculator for Fuel C.pdf:application/pdf;Schneider and Scopatz - 2016 - An Integrated Fuel Depletion Calculator for Fuel C.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\T8ZXE4A9\\Schneider and Scopatz - 2016 - An Integrated Fuel Depletion Calculator for Fuel C.pdf:application/pdf},
}

@article{triplett_prism:_2012,
	title = {{PRISM}: {A} {Competitive} {Small} {Modular} {Sodium}-{Cooled} {Reactor}},
	volume = {178},
	issn = {0029-5450, 1943-7471},
	shorttitle = {{PRISM}},
	url = {https://www.tandfonline.com/doi/full/10.13182/NT178-186},
	doi = {10.13182/NT178-186},
	language = {en},
	number = {2},
	urldate = {2020-02-13},
	journal = {Nuclear Technology},
	author = {Triplett, Brian S. and Loewen, Eric P. and Dooies, Brett J.},
	month = may,
	year = {2012},
	pages = {186--200},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\LLYAIAFM\\NT178-186.html:text/html;Triplett et al. - 2012 - PRISM A Competitive Small Modular Sodium-Cooled R.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\Y6VKI4HH\\Triplett et al. - 2012 - PRISM A Competitive Small Modular Sodium-Cooled R.pdf:application/pdf},
}

@article{bae_deep_2020,
	title = {Deep learning approach to nuclear fuel transmutation in a fuel cycle simulator},
	volume = {139},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454919307406},
	doi = {10.1016/j.anucene.2019.107230},
	abstract = {We trained a neural network model to predict Pressurized Water Reactor (PWR) Used Nuclear Fuel (UNF) composition given initial enrichment and burnup. This quick, flexible, medium-fidelity method to estimate depleted PWR fuel assembly compositions is used to model scenarios in which the PWR fuel burnup and enrichment vary over time. The Used Nuclear Fuel Storage, Transportation \& Disposal Analysis Resource and Data System (UNF-ST\&DARDS) Unified Database (UDB) provided a ground truth on which the model trained. We validated the model by comparing the U.S. UNF inventory profile predicted by the model with the UDB UNF inventory profile. The neural network yields less than 1\% error for UNF inventory decay heat and activity and less than 2\% error for major isotopic inventory. The neural network model takes 0.27 s for 100 predictions, compared to 118 s for 100 Oak Ridge Isotope GENeration (ORIGEN) calculations. We also implemented this model into Cyclus, an agent-based Nuclear Fuel Cycle (NFC) simulator, to perform rapid, medium-fidelity PWR depletion calculations. This model also allows discharge of batches with assemblies of varying burnup. Since the original private data cannot be retrieved from the model, this trained model can provide open-source depletion capabilities to NFC simulators. We show that training an artificial neural network with a dataset from a complex fuel depletion model can provide rapid, medium-fidelity depletion capabilities to large-scale fuel cycle simulations.},
	language = {en},
	urldate = {2020-01-07},
	journal = {Annals of Nuclear Energy},
	author = {Bae, Jin Whan and Rykhlevskii, Andrei and Chee, Gwendolyn and Huff, Kathryn D.},
	month = may,
	year = {2020},
	keywords = {agent based modeling, Artificial neural network, Depletion, Finite elements, Hydrologic contaminant transport, Machine learning, Molten salt breeder reactor, Molten salt reactor, MOOSE, Multiphysics, nuclear engineering, Nuclear fuel cycle, Object orientation, Online reprocessing, Parallel computing, Python, Reactor physics, repository, Salt treatment, Simulation, Spent nuclear fuel, Systems analysis},
	pages = {107230},
	file = {Bae et al. - 2020 - Deep learning approach to nuclear fuel transmutati.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\63AWUGKG\\63AWUGKG.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\U7IJI82D\\S0306454919307406.html:text/html},
}

@book{deb_multi-objective_2001,
	title = {Multi-objective optimization using evolutionary algorithms},
	volume = {16},
	isbn = {0-471-87339-X},
	publisher = {John Wiley \& Sons},
	author = {Deb, Kalyanmoy},
	year = {2001},
}

@techreport{mulder_pebble_1999,
	title = {Pebble bed reactor with equalised core power distribution inherently safe and simple},
	url = {https://juser.fz-juelich.de/record/820874/},
	abstract = {Based an the physical properties of pebble bed reactors, a multitude of variations are possible in the layout of the fuel and fuelling schemes. These properties are being exploited in a conceptual design, offering an attractive layout in terms of the inter-related aspects of safety, economy and simplicity. Advantages of this layout are highlighted by means of a direct comparison to a similar reactor characterised by a conventional fuelling scheme. The proposed concept is characterised by the following: In the OTTO (\${\textbackslash}underline\{O\}\$nce \${\textbackslash}underline\{T\}\$hrough \${\textbackslash}underline\{T\}\$hen \${\textbackslash}underline\{O\}\$ut) fuelling scheme the fuel spheres pass through the core once only. Therefore the fuel recirculation subsystems may be negated in the design. The PAP2 (\${\textbackslash}underline\{P\}\$ower \${\textbackslash}underline\{A\}\$djusted by-\${\textbackslash}underline\{P\}\$oison) fuelling scheme involves adding of pebbles with burnable poison that will lead to a strong flattening of the axial core power density. These absorber spheres contain coated particles of B\$\_\{4\}\$C instead of fuel. In the radial direction flattening of the power density is achieved by increasing the loading of graphite spheres into the central fuelling channel (2-zone fuelling). The advantages of a relatively high power performance (250 MW\$\_\{th\}\$), a high heavy metal loading per fuel element (14g\$\_\{HM\}\$), and high burnup (120 MWd/Kg\$\_\{HM\}\$ can be directly translated into an economical advantage. Lowly enriched uranium is employed as fuel which provides a highly proliferation resistant solution when coupled to the high burnup and oncethrough only cycle. The control capability includes unlimited power variations within the operational range of 100-20-100\%. In the proposed concept the reactor is coupled to a power conversion unit which employs a direct cycle helium power turbine. - During a loss of coolant (DLOFC = Depressurised Loss Of Forced Coolant) event, the fuel element temperature is passively limited below 1600 °C, thus avoiding any radioactive release. Computationally the reactor is simulated by means of the VSOP (\${\textbackslash}underline\{V\}\$ery \${\textbackslash}underline\{S\}\$uperior \${\textbackslash}underline\{O\}\$ld \${\textbackslash}underline\{P\}\$rograms) staple of codes. For this purpose the following extensions to the code have been developed: A so-called onion-skin burnup model is introduced to calculate the burnup of the B\$\_\{4\}\$C kernels. Within the absorber spheres the burnup of the coated (B\$\_\{4\}\$C) particles are being followed in a nurnher of separate fiel zones. Based an experimental findings a fuel sphere flog scheine has been developed, which moves downward in parallel in the top area, while the bottorn area is re-organised in a funnel shape towards die de fuelling pipe in accordance with the angle of the conus and discharge rate. A 3-D geometric modeller, FIRZIT (i.e. in \${\textbackslash}phi\$-r-z-ordinates) has been exclusively developed for modelling the so-called noses, employed for housing the cold shut down system in a core with 3,5 m diarneter. This enables the modelling of various pebble flow schernes in azimuthal segments. [...] Mulder, E. J.},
	language = {en},
	number = {FZJ-2016-06138},
	urldate = {2021-02-25},
	institution = {Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag},
	author = {Mulder, E. J.},
	year = {1999},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\BNWJUVGD\\820874.html:text/html},
}

@article{romano_depletion_2021,
	title = {Depletion capabilities in the {OpenMC} {Monte} {Carlo} particle transport code},
	abstract = {A depletion solver has been implemented in OpenMC and is described herein. The depletion solver is implemented in Python and interfaces with OpenMC’s transport solver through a C++ application programming interface, which enables an in-memory transport-depletion coupling. Multiple integration methods for advancing in time have been implemented and exhibit tradeoffs in cost, accuracy, and memory use. For all time integration methods, evaluation of the matrix exponential is performed by using the incomplete partial fraction form of the Chebyshev rational approximation method.},
	language = {en},
	journal = {Annals of Nuclear Energy},
	author = {Romano, Paul K},
	year = {2021},
	pages = {15},
	file = {Romano - 2021 - Depletion capabilities in the OpenMC Monte Carlo p.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\98FZYZ5G\\Romano - 2021 - Depletion capabilities in the OpenMC Monte Carlo p.pdf:application/pdf},
}

@article{teuchert_core_1975,
	title = {Core physics and fuel cycles of the pebble bed reactor},
	volume = {34},
	issn = {0029-5493},
	url = {https://www.sciencedirect.com/science/article/pii/0029549375901600},
	doi = {10.1016/0029-5493(75)90160-0},
	abstract = {A high degree of flexibility for the application of the pebble bed HTR results from the size of the fuel elements and the continuous loading of fuel during operation. The OTTO loading scheme (once-through-then-out) allows the gas outlet temperature to be increased up to 1190°C as desired. Different fuel cycles can be used in the same reactor. The highly enriched uranium/thorium fuel cycle allows favourable utilization of the fissile reserves. For a conventional design the net consumption is 467 g/GWd(th), and this figure can be reduced to 58 g/GWd(th) for the advanced variant, achieving the breeding ratio 0.95. The advantage of the low enrichment uranium fuel cycle is the direct in situ utilization of the bred plutonium, being as high as 87\%, which reduces the demand for short-term recycling. The reactor allows change over between the different cycles under full power operation.},
	language = {en},
	number = {1},
	urldate = {2022-03-27},
	journal = {Nuclear Engineering and Design},
	author = {Teuchert, E. and Rütten, H. J.},
	month = oct,
	year = {1975},
	pages = {109--118},
	file = {ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\HMYA4NWM\\0029549375901600.html:text/html;Teuchert and Rütten - 1975 - Core physics and fuel cycles of the pebble bed rea.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\XFEMNZAR\\Teuchert and Rütten - 1975 - Core physics and fuel cycles of the pebble bed rea.pdf:application/pdf},
}

@misc{richter_zoerichterphlox_2022,
	title = {{ZoeRichter}/phlox: {Version} 1.1},
	shorttitle = {{ZoeRichter}/phlox},
	url = {https://zenodo.org/record/6451576},
	abstract = {Corresponds to version used in MS thesis. Dated 11/20/21},
	urldate = {2021-11-20},
	publisher = {Zenodo},
	author = {Richter, Zoë and Fairhurst, Roberto and Türkmen, Mehmet and Huff, Katy and Dotson, Sam},
	month = apr,
	year = {2022},
	doi = {10.5281/zenodo.6451576},
	file = {Zenodo Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\YTI3VPQD\\5715933.html:text/html},
}

@techreport{hamilton_htgr_1976,
	title = {{HTGR} spent fuel composition and fuel element block flow},
	url = {https://www.osti.gov/biblio/7157851},
	abstract = {The U.S. Department of Energy's Office of Scientific and Technical Information},
	language = {English},
	number = {GA-A-13886(Vol.1)},
	urldate = {2021-06-03},
	institution = {General Atomic Co., San Diego, Calif. (USA)},
	author = {Hamilton, C. J. and Holder, N. D. and Pierce, V. H. and Robertson, M. W.},
	month = jul,
	year = {1976},
	doi = {10.2172/7157851},
	note = {GA-A13886},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\D3BMXEDI\\Hamilton et al. - 1976 - HTGR spent fuel composition and fuel element block.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\J6X7HL7I\\7157851.html:text/html},
}

@techreport{hussain_advances_2018,
	address = {Vienna, Austria},
	type = {A {Supplement} to: {IAEA} {Advanced} {Reactors} {Information} {System} ({ARIS})},
	title = {Advances in {Small} {Modular} {Reactor} {Technology} {Developments}},
	url = {http://aris.iaea.org},
	abstract = {The driving forces in the development of SMRs are their specific characteristics. They can be deployed incrementally to closely match increasing energy demand resulting in a moderate financial commitment for countries or regions with smaller electricity grids. SMRs show the promise of significant cost reduction through modularization and factory construction which should further improve the construction schedule and reduce costs. In the area of wider applicability SMR designs and sizes are better suited for partial or dedicated use in non-electrical applications such as providing heat for industrial processes, hydrogen production or sea-water desalination. Process heat or cogeneration results in significantly improved thermal efficiencies leading to a better return on investment. Some SMR designs may also serve niche markets, for example to burn nuclear waste. Booklets on the status of SMR technology developments have been published in 2012, 2014 and 2016. The objective is to provide Member States with a concise overview of the latest status of SMR designs. This booklet is reporting the advances in design and technology developments of SMRs of all the major technology lines within the category of SMRs. It covers land based and marine based water-cooled reactors, high temperature gas cooled reactors, liquid metal, sodium and gas-cooled fast neutron spectrum reactors and molten salt reactors. The content on the specific SMRs is provided by the responsible institute or organization and is reproduced, with permission, in this booklet.},
	institution = {Nuclear Power Technology Development Section, Division of Nuclear Power of the IAEA Department of Nuclear Energy},
	author = {Hussain, M. and Reitsma, F. and Subki, M.H. and Kiuchi, H.},
	month = sep,
	year = {2018},
	file = {IAEA - 2018 - Advances in Small Modular Reactor Technology Devel.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\V3DHFDXG\\IAEA - 2018 - Advances in Small Modular Reactor Technology Devel.pdf:application/pdf},
}

@techreport{notz_overview_1976,
	title = {Overview of {HTGR} fuel recycle},
	url = {https://www.osti.gov/biblio/4152968},
	abstract = {An overview of HTGR fuel recycle is presented, with emphasis placed on reprocessing and fuel kernel refabrication. Overall recycle operations include (1) shipment and storage, (2) reprocessing, (3) refabrication, (4) waste handling, and (5) accountability and safeguards. (auth)},
	language = {English},
	number = {ORNL-TM-4747},
	urldate = {2022-08-29},
	institution = {Oak Ridge National Lab., Tenn. (USA)},
	author = {Notz, K. J.},
	month = jan,
	year = {1976},
	doi = {10.2172/4152968},
	file = {Notz - An Overview of HTGR Fuel Recycle.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\IUIK6MJH\\Notz - An Overview of HTGR Fuel Recycle.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\P2GX3Y8V\\4152968.html:text/html},
}

@misc{us_nuclear_regulatory_commission_stages_2020,
	title = {Stages of the {Nuclear} {Fuel} {Cycle}},
	urldate = {2022-02-25},
	author = {{U.S. Nuclear Regulatory Commission}},
	month = dec,
	year = {2020},
	note = {Publication Title: NRC Web
Published:  https://www.nrc.gov/materials/fuel-cycle-fac/stages-fuel-cycle.html},
}

@misc{powersim_powersim_nodate,
	title = {{PowerSim} {Software}},
	url = {https://powersim.com/},
	abstract = {Powersim Software; the developer of pForecast and the Powersim Studio 10 tools for System Dynamics modelling, simulations and uncertainty analysis.},
	language = {en-GB},
	urldate = {2022-02-10},
	author = {{PowerSim}},
	note = {Publication Title: Powersim Software},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\463XIV3P\\powersim.com.html:text/html},
}

@article{richards_application_2021,
	title = {Application of sensitivity analysis in {DYMOND}/{Dakota} to fuel cycle transition scenarios},
	volume = {7},
	copyright = {© S. Richards and B. Feng, Published by EDP Sciences, 2021},
	issn = {2491-9292},
	doi = {10.1051/epjn/2021024},
	abstract = {The ability to perform sensitivity analysis has been enabled for the nuclear fuel cycle simulator DYMOND through its coupling with the design and analysis toolkit Dakota. To test and demonstrate these new capabilities, a transition scenario and multi-parameter study were devised. The transition scenario represents a partial transition from the US nuclear fleet to a closed fuel cycle with small modular LWRs and fast reactors fueled by reprocessed used nuclear fuel. Four uncertain parameters in this transition were studied – start date of reprocessing, total reprocessing capacity, the nuclear energy demand growth, and the rate at which the fast reactors are deployed – with respect to their impact on four response metrics. The responses – total natural uranium consumed, maximum annual enrichment capacity required, total disposed mass, and total cost of the nuclear fuel cycle – were chosen based on measures known to be of interest in transition scenarios [] and to be significantly impacted by the varying parameters. Analysis of this study was performed both from the direct sampling and through surrogate models developed in Dakota to calculate the global sensitivity measures Sobol’ indices. This example application of this new capability showed that the most consequential parameter to most metrics was the share of new build capacity that is fast reactors. However, for the cost metric, the scaling factor of the energy demand growth was significant and had synergistic behavior with the fast reactor new build share.},
	language = {en},
	urldate = {2022-02-09},
	journal = {EPJ Nuclear Sciences \& Technologies},
	author = {Richards, S. and Feng, B.},
	year = {2021},
	note = {Published: = https://www.epj-n.org/articles/epjn/abs/2021/01/epjn210022/epjn210022.html},
	pages = {26},
	annote = {Publisher: EDP Sciences},
	file = {Application of sensitivity analysis in DYMOND_Dakota to fuel cycle transition scenarios - 1841572.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\HHJRD9YK\\Application of sensitivity analysis in DYMOND_Dakota to fuel cycle transition scenarios - 1841572.pdf:application/pdf;Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\Q3G5TYM8\\BYDIMIBN.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\I5FBNX4K\\epjn210022.html:text/html},
}

@techreport{feng_sensitivity_2020,
	title = {Sensitivity and {Uncertainty} {Quantification} of {Transition} {Scenario} {Simulations}},
	abstract = {This report documents the first collective attempt at developing and applying capabilities to quantify uncertainties, assess parametric sensitivities, and optimize multiple parameters and metrics in fuel cycle simulations generated by the SA\&I Campaign. To do this, external codes that were designed to perform sensitivity analysis and uncertainty quantification (SA\&UQ) needed to be coupled to the SA\&I Campaign’s nuclear fuel cycle simulators (NFCS). In FY20, two approaches were pursued: 1) coupling Cyclus to an ORNL-internal code called MOT (Metaheuristic Optimization Tool) and 2) coupling DYMOND to the opensource SA\&UQ tool kit Dakota. The primary objective of having these NFCS/SA\&UQ coupled capabilities is to better inform DOE-NE and other stakeholders on the results generated from the NFCS. For a given set of fuel cycle strategies, policies, and technology assumptions that make up a fuel cycle scenario, these NFCS have traditionally been used by the SA\&I Campaign to provide quantitative answers in terms of year-by-year mass flows, infrastructure requirements, costs, etc. With these newly developed coupled capabilities, the SA\&I Campaign can now efficiently simulate hundreds or thousands of these scenarios, sample large ranges of parameters and assumptions, and use the unique features of the SA\&UQ tools to process the data. This enables providing answers with known and propagated uncertainties, determining the sensitivity of important metrics to different parameters and assumptions, quantifying how much fuel cycle and technology parameters impact each other, and producing optimized fuel cycle strategies for single and multiple variables. To demonstrate these new capabilities, the Cyclus/MOT was used to model several scenarios ranging from simple fleet retirements to transitions to advanced reactors. Specifically, for a transition scenario from LWRs to SFRs and advanced LWRs, uncertainty quantification, sensitivity analysis, and optimization studies were applied to cases involving single and multiple parameter (input) and single and multiple metric (output) variations. In addition, a similar transition scenario was modeled to demonstrate how to optimize the reprocessing capacity parameter to minimize two performance metrics while taking into account uncertainties from two other parameters. Lastly, a depletion module based on SCALE/ORIGEN was added in Cyclus to simulate the third scenario that was designed to quantify the impact of the modeling assumption that all LWR used nuclear fuel have the same burnup. The newly developed DYMOND/Dakota capability was also applied to a transition scenario from the existing fleet to small modular reactors and fast reactors. This particular scenario involves not only explicit isotopic depletion via ORIGEN-2, but also includes multirecycling and utilizing the criticality search feature to determine the fresh fuel composition of recycled fuel, a feature unique to the DYMOND NFCS. A large database of simulations were run with 4 main parameters that were sampled: start date of reprocessing, reprocessing capacity, energy demand growth rate, and advanced reactor share of the fleet. The 4 main metrics were uranium consumption, enrichment requirements, waste generation, and levelized cost of electricity using data from the Cost Basis Report. The demonstrated SA\&UQ results include those that inform on how to choose parameters to avoid “failed” scenarios, Sobol’ indices that inform on the importance of various parameters individually and synergistically, and Analysis of Variance (ANOVA) studies that decompose parameter ranges into groups and informs on whether variations are statistically significant.},
	language = {English},
	number = {ANL/NSE-20/38},
	urldate = {2022-02-09},
	institution = {Argonne National Lab. (ANL), Argonne, IL (United States)},
	author = {Feng, B. and Richards, S. and Bae, J. and Davidson, E. and Worrall, A. and Hays, R.},
	month = sep,
	year = {2020},
	note = {Published: = https://www.osti.gov/biblio/1670703},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\AUJ5QGB5\\8TAP3BE3.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\TWK3RAEK\\1670703.html:text/html},
}

@inproceedings{powers_fully_2014,
	address = {Kyoto, Japan},
	title = {{FULLY} {CERAMIC} {MICROENCAPSULATED} {FUELS}: {CHARACTERISTICS} {AND} {POTENTIAL} {LWR} {APPLICATIONS}},
	abstract = {This paper summarizes the characteristics of the fully ceramic microencapsulated (FCM) fuel concept and two potential light water reactor (LWR) applications of FCM fuels: for actinide management and as an accident tolerant fuel (ATF). Recent progress in FCM fuel development includes production of uranium mononitride kernels, fabrication of FCM pellets and pins, and irradiation testing of matrix samples and FCM pellets. Potential applications of FCM fuel in LWRs appear promising based upon studies performed by several organizations; however, further efforts are needed to investigate various design aspects in further detail and explore promising new areas of research such as new fuel pin and assembly designs or alternate materials of interest. Current challenges in FCM fuel development and LWR applications for FCM fuels include low heavy metal fuel loading densities and increased uncertainties in analysis due to several different factors. Overall, LWR FCM concepts appear feasible for both actinide management and as an ATF.},
	language = {en},
	author = {Powers, Jeffrey J and Worrall, Andrew and Terrani, Kurt A and Gehin, Jess C and Snead, Lance L},
	year = {2014},
	pages = {16},
	file = {Powers et al. - 2014 - FULLY CERAMIC MICROENCAPSULATED FUELS CHARACTERIS.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\LVNCIQAE\\KAL8M2SG.pdf:application/pdf},
}

@inproceedings{snead_fully_2011,
	title = {Fully {Ceramic} {Microencapsulated} {Fuels}: {A} {Transformational} {Technology} for {Present} and {Next} {Generation} {Reactors}},
	volume = {104},
	abstract = {The technology of microencapsulated fuel, in the form of TRistructural‐ISOtropic (TRISO) ceramics, was first developed for large High Temperature Gas Cooled systems such as the German THTR‐300 and the US Ft. St. Vrain reactors. Recently, significant performance improvements of TRISO fuels have been achieved through the US AGR program whereby newly improved and fabricated fuel from ORNL has been irradiated at the ATR reactor at INL to a fluence more than twice as large as the previous record. This recently invigorated effort towards the understanding and improved performance of microencapsulated fuels has spurred study into potential new applications for such fuel forms. Example applications include the destruction of transuranics (TRU) contained in spent fuel and replacement of standard UO2 fuel in commercial LWRs, or as the fuel of the next generation fluoride salt cooled reactors.},
	language = {en},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	author = {Snead, L L and Venneri, F and Kim, Y and Terrani, K A and Tulenko, J E and Forsberg, C W and Peterson, P F and Lahoda, E J},
	year = {2011},
	pages = {668--674},
	file = {Snead et al. - Fully Ceramic Microencapsulated Fuels A Transform.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\34FZ6ZMS\\GCR2WMZ2.pdf:application/pdf},
}

@misc{us_nuclear_regulatory_commission_centrus_2021,
	title = {Centrus {Energy} {Corp}. (formerly {USEC} {Inc}.) {Gas} {Centrifuge} {Enrichment} {Facility} {Licensing}},
	urldate = {2022-02-08},
	author = {{U.S. Nuclear Regulatory Commission}},
	month = may,
	year = {2021},
	note = {Publication Title: NRC Web},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\E5BPKZ7G\\usecfacility.html:text/html},
}

@techreport{nelson_foreign_2010,
	address = {Belgium},
	title = {Foreign research reactor uranium supply program: {The} {Y}-12 national security complex process},
	shorttitle = {Foreign research reactor uranium supply program},
	abstract = {The Foreign Research Reactor (FRR) Uranium Supply Program at the Y-12 National Security Complex supports the nonproliferation objectives of the HEU Disposition Program, the Reduced Enrichment Research and Test Reactors (RERTR) Program, and the United States FRR Spent Nuclear Fuel (SNF) Acceptance Program The Y-12 National Nuclear Security Administration (NNSA) Y-12 Site Office maintains the prime contracts with foreign governments for the supply of Low-Enriched Uranium (LEU) for their research reactors The LEU is produced by down blending Highly Enriched Uranium (HEU) that has been declared surplus to the US national defense needs The down blending and sale of the LEU supports the Surplus HEU Disposition Program Record of Decision to make the HEU non-weapons usable and to recover the economic value of the uranium to the extent feasible This program supports the important US government and nuclear nonproliferation commitment to serve as a reliable and cost-effective uranium supplier for those foreign research reactors that are converting or have converted to LEU fuel under the guidance of the NNSA RERTR Program In conjunction with the FRR SNF Acceptance Program which supports the global nonproliferation efforts to disposition US-origin HEU, the Y-12 FRR Uranium Supply Program can provide the LEU for the replacement fuel fabrication In addition to feedstock for fuel fabrication, Y-12 supplies LEU for target fabrication for medical isotope production The Y-12 process uses supply forecasting tools, production improvements and efficient delivery preparations to successfully support the global research reactor community},
	number = {978-92-95064-10-2},
	author = {Nelson, T. and Eddy, B.G.},
	year = {2010},
	pages = {8},
	annote = {INIS-BE–10K0001 INIS Reference Number: 41064167},
	file = {Nelson and Eddy - 2010 - Foreign research reactor uranium supply program T.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\H3T9Q5FC\\6LVK6WGN.pdf:application/pdf},
}

@misc{nuclear_energy_institute_us_2021,
	title = {U.{S}. {Nuclear} {Plant} {License} {Information}},
	url = {https://www.nei.org/resources/statistics/us-nuclear-plant-license-information},
	abstract = {License information for operating plants, including operation, commercial operation and expiration dates and net summer capacity.},
	language = {en},
	urldate = {2022-02-03},
	author = {{Nuclear Energy Institute}},
	month = may,
	year = {2021},
	note = {Publication Title: Nuclear Energy Institute},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\DR7BAFM4\\us-nuclear-plant-license-information.html:text/html},
}

@techreport{us_energy_information_administration_monthly_2022,
	address = {Washington, D.C.},
	type = {Technical {Report}},
	title = {Monthly {Energy} {Review} – {January} 2022},
	url = {https://www.eia.gov/totalenergy/data/monthly/},
	language = {en},
	institution = {U.S. Energy Information Administration},
	author = {{U.S. Energy Information Administration}},
	month = jan,
	year = {2022},
	pages = {276},
	file = {2022 - Monthly Energy Review – January 2022.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\BNHEV75R\\2022 - Monthly Energy Review – January 2022.pdf:application/pdf},
}

@misc{noauthor_us_nodate,
	title = {U.{S}. nuclear industry - {U}.{S}. {Energy} {Information} {Administration} ({EIA})},
	url = {https://www.eia.gov/energyexplained/nuclear/us-nuclear-industry.php},
	urldate = {2022-02-02},
	file = {U.S. nuclear industry - U.S. Energy Information Administration (EIA):C\:\\Users\\abachmann\\Zotero\\storage\\CHSXNYIX\\us-nuclear-industry.html:text/html},
}

@misc{noauthor_us_2022,
	title = {U.{S}. {Nuclear} {Generating} {Statistics}},
	url = {https://www.nei.org/resources/statistics/us-nuclear-generating-statistics},
	abstract = {U.S. nuclear generating statistics from 1977-2019, including megawatt-hours generated by nuclear energy, capacity factor, nuclear fuel share and total electricity generation.},
	language = {en},
	urldate = {2022-02-02},
	month = aug,
	year = {2022},
	note = {Publication Title: Nuclear Energy Institute},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\4UWZEPSQ\\us-nuclear-generating-statistics.html:text/html},
}

@article{koning_status_2011,
	title = {Status of the {JEFF} nuclear data library},
	volume = {59},
	doi = {10.3938/jkps.59.1057},
	abstract = {The status of the Joint Evaluated Fission and Fusion file (JEFF) is described. Recently, the JEFF-3.1.1 nuclear data library was released, and shortly after adopted by the French nuclear power industry for inclusion in their production and analysis codes. Recent updates include actinide evaluations, materials evaluations that have emerged from various European nuclear data projects, the activation library, the decay data and fission yield sub-libraries, and fusion-related data files from the European F4E project. The revisions were motivated by the availability of new measurements, modelling capabilities and trends from integral experiments. Validations have been performed, mainly for criticality, reactivity temperature coefficients, fuel inventory, decay heat and shielding of thermal and fast systems. The next release of the library, JEFF-3.2, will be discussed. This will contain among others a significant increase of covariance data evaluations, modern evaluations for various structural materials, a larger emphasis on minor actinides and addition of high-quality gamma production data for many fission products.},
	journal = {Journal- Korean Physical Society},
	author = {Koning, Arjan and Bauge, E. and Dean, C.J. and Dupont, Emmeric and U., Fischer and Forrest, R.A. and Jacqmin, R. and Leeb, Helmut and Kellett, Mark and Mills, R.W. and C., Nordborg and Pescarini, M. and Rugama, Yolanda and P., Rullhusen},
	month = aug,
	year = {2011},
	pages = {1057--1062},
	file = {Koning et al. - 2011 - Status of the JEFF nuclear data library.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\ZFW8E5SG\\Koning et al. - 2011 - Status of the JEFF nuclear data library.pdf:application/pdf},
}

@article{sadegh-noedoost_investigations_2020,
	title = {Investigations of the fresh-core cycle-length and the average fuel depletion analysis of the {NuScale} core},
	volume = {136},
	issn = {0306-4549},
	url = {https://www.sciencedirect.com/science/article/pii/S0306454919304979},
	doi = {10.1016/j.anucene.2019.106995},
	abstract = {Fresh cores with a few changes on the fuel enrichment and/or gadolinium content of the Fuel Assemblies (FAs) are proposed for a typical PWR-Small Modular Reactor called NuScale. Many neutronics as well as Thermal Hydraulics (TH) Core Design Basis Limits for the first-cycle of the proposed fresh core are fully studied and verified herein. In addition, the coupled TH-neutronic calculations of the core are performed using RELAP5-MCNP codes. The burnup calculation for the core is performed using MCNPX 2.7 to investigate the core first-cycle-length. The excess reactivity as well as power peaking are studied to find the first-cycle-length. Average core fuel depletion are also taken into account; and masses of produced fission fragments and build up plutonium isotopes as well as the remained mass of uranium isotopes (and Gd) are computed at the EOC (first cycle of 730 days).},
	language = {en},
	urldate = {2022-01-31},
	journal = {Annals of Nuclear Energy},
	author = {Sadegh-Noedoost, A. and Faghihi, F. and Fakhraei, A. and Amin-Mozafari, M.},
	month = feb,
	year = {2020},
	keywords = {Small modular reactor, Core design basis limits, First cycle-length, Fuel depletion analysis, Makxsf module, MCNPX2.7/MCNP5 and RELAP5/SCDAP 3.4},
	pages = {106995},
	file = {Sadegh-Noedoost et al. - 2020 - Investigations of the fresh-core cycle-length and .pdf:C\:\\Users\\abachmann\\Zotero\\storage\\22H7X5B2\\Sadegh-Noedoost et al. - 2020 - Investigations of the fresh-core cycle-length and .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\TVNQIVTG\\S0306454919304979.html:text/html},
}

@article{suk_simulation_2021,
	title = {Simulation of a {NuScale} core design with the {CASL} {VERA} code},
	volume = {371},
	issn = {0029-5493},
	url = {https://www.sciencedirect.com/science/article/pii/S0029549320304507},
	doi = {10.1016/j.nucengdes.2020.110956},
	abstract = {Three-dimensional (3D) full-core calculations are an integral part of fuel reload design for today’s light water reactors (LWRs). The current approaches are typically based on the nodal diffusion codes that calculate criticality state points and power distributions as a function of burnup. The CASL VERA (Consortium for Advanced Simulation of Light Water Reactors, Virtual Environment for Reactor Applications) code represents one of the latest advancements in 3D full-core calculation analysis based on transport theory methods employing the Method of Characteristics (MOC) and coupled multi-physics. In this article, a publicly released version of the NuScale reactor core is analysed with the VERA code (version 3.9 and 4.1) and contrasted against some static Serpent and Polaris based simulations. The analysis shows an excellent agreement for the lattice-level calculations as well as with some of the 3D full-core models. However, larger deviations were found in cases with heavy reflector models, whereby the reflector composition was found to impact the differences between the VERA and Serpent results. In this analysis, it was determined that greater than 90\% stainless steel content in the heavy reflector leads to higher deviations between the VERA results and the Serpent results. The burnup calculations showed that the presence of the heavy reflector extends the cycle length and also leads to a flatter power distribution in the core, which can generally be interpreted as more efficient.},
	language = {en},
	urldate = {2022-01-31},
	journal = {Nuclear Engineering and Design},
	author = {Suk, Pavel and Chvála, Ondřej and Maldonado, G. Ivan and Frýbort, Jan},
	month = jan,
	year = {2021},
	keywords = {Serpent, 3D full core calculations, CASL VERA, Loads optimization, NuScale, TH coupling},
	pages = {110956},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\SHTANPB9\\887KYAFX.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\IVCGE8Z3\\S0029549320304507.html:text/html},
}

@article{carlson_economic_2020,
	title = {An {Economic} {Cost} {Assessment} on {HALEU} {Fuels} for {Small} {Modular} {Reactors}},
	volume = {2020},
	issn = {1687-6075},
	url = {https://www.hindawi.com/journals/stni/2020/8815715/},
	doi = {10.1155/2020/8815715},
	abstract = {Small modular reactors (SMRs) are currently being considered as future investments for commercial entities due to perceived advantages over traditional large-scale power reactors, particularly their considerably lower capital costs. One strategy for lowering the levelized cost of electricity (LCOE) of SMRs is to increase their burnup by utilizing high-assay low-enriched uranium (HALEU) fuels, which range from 5 to 20 weight percent (w/o) of U-235. By increasing fuel enrichment to HALEU levels, with higher specific fuel costs compared to standard enrichment, a plant may achieve an increased capacity factor by extending its fuel cycle and thereby reducing average yearly fuel supply costs. It is expected that the benefits of optimizing fuel enrichment to extend a reactor’s fuel cycle outweigh the added cost due to more expensive fuel. In this paper, the net benefit of extending an SMR’s fuel cycle by enriching uranium fuel to HALEU levels was estimated using 2017 nuclear fuel production market data with NuScale’s 160 MWt SMR design as a case study. It was found that, for NuScale’s design, plant LCOE decreased with increasing cycle length enabled by higher fuel enrichment. It was also observed that doubling cycle time from 24 months to 48 months netted each reactor a 1.23 \$/MWh reduction in LCOE. The total savings for a 12-module SMR design were estimated to be around \$5,840,000 per year. Therefore, utilizing HALEU fuel in SMRs can vastly improve their economic efficiency.},
	language = {en},
	urldate = {2022-01-27},
	journal = {Science and Technology of Nuclear Installations},
	author = {Carlson, Liam and Wu, Zeyun and Olson, James and Liu, Li (Emily)},
	month = dec,
	year = {2020},
	pages = {e8815715},
	annote = {Publisher: Hindawi},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\AC4N95ZK\\N9CKFW6G.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\MUECWKM2\\8815715.html:text/html},
}

@misc{nuscale_chapter_2020,
	title = {Chapter {Four} {Reactor}},
	shorttitle = {{NuScale} {Final} {Safety} {Analysis} {Report}},
	url = {https://www.nrc.gov/reactors/new-reactors/design-cert/nuscale.html},
	abstract = {NuScale Standard Plant Design Certification Application},
	publisher = {US NRC},
	author = {{NuScale}},
	month = jul,
	year = {2020},
	annote = {Rev. 5},
	file = {ML20224A492.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\RTVA62ME\\ML20224A492.pdf:application/pdf},
}

@misc{nuscale_chapter_2020-1,
	title = {Chapter {One} {Introdcution} and {General} {Description} of the {Plant}},
	shorttitle = {{NuScale} {Final} {Safety} {Analysis} {Report}},
	url = {https://www.nrc.gov/reactors/new-reactors/design-cert/nuscale.html},
	abstract = {NuScale Standard Plant Design Certification Application},
	publisher = {US NRC},
	author = {{NuScale}},
	month = jul,
	year = {2020},
	annote = {Rev. 5},
	file = {NuScale - 2020 - Chapter One Introdcution and General Description o.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\39RV5343\\NuScale - 2020 - Chapter One Introdcution and General Description o.pdf:application/pdf},
}

@article{carlson_implications_2022,
	title = {Implications of {HALEU} fuel on the design of {SMRs} and micro-reactors},
	volume = {389},
	issn = {0029-5493},
	url = {https://www.sciencedirect.com/science/article/pii/S0029549322000024},
	doi = {10.1016/j.nucengdes.2022.111648},
	abstract = {Since the construction of the first commercial nuclear power plant in 1957, the nuclear power industry has operated under the philosophy of economy of scale - the idea that increased power plant size accounts for higher economic efficiency. However, there has been a recent shift in direction; small modular reactors (SMRs) and micro-reactors are being considered as potentially wise investments for commercial power producers in that they can provide advantages that large-scale reactors may not possess in terms of reactor safety and investment risk. However, this may come at the risk of a higher levelized cost of electricity (LCOE). LCOE may be reduced by enriching the fuel passed its regulated limit of 5 wt\% (w/o) 235U. The high assay low-enriched uranium (HALEU) fuel (5–20 w/o 235U) is introduced to increase the plant capacity factor, which thereby decrease fuel supply costs and reduce the LCOE. While decreasing plant LCOE seems like a clear advantage, several issues may result from increasing enrichments to the HALEU level in an SMR or micro-reactor design. This paper aims to shed light on these issues and address how they may affect the overall reactor design by using HALEU fuels in these reactors. This paper first discusses the notable effects on a reactor design with higher enrichment, then analyzes a SMR case study based on the NuScale’s 160 MWth SMR design. The case study reveals that the SMR with higher enriched fuel was able to double both fuel burnup and cycle time with an average core enrichment of 8.34 w/o and a maximum average assembly enrichment of 9.10 w/o. Moreover, this higher enriched core was found to operate with a maximum global peaking factor of 1.86, well below the published limit of 2.0. Likewise, the maximum axial flux offset of −2.4\% and the maximum boron concentration of 1757 ppm both remain within their respective safety constraints. Notable fission poisons, such as 149Sm and 135Xe, were also found to sharply increase in the HALEU core. Additionally, the average fuel temperature and peak cladding temperature fell within their respective safety constraints. Core-averaged flux, fluence, cladding creep, and post-shutdown decay heat were also investigated. Lastly, the higher enriched core was found to reduce LCOE by approximately 1.23 \$/MWh.},
	language = {en},
	urldate = {2022-01-26},
	journal = {Nuclear Engineering and Design},
	author = {Carlson, Liam and Miller, James and Wu, Zeyun},
	month = apr,
	year = {2022},
	pages = {111648},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\PR848KBT\\PRPFPFA9.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\JU4CTF55\\S0029549322000024.html:text/html},
}

@misc{nagley_ha-leu_2020,
	title = {{HA}-{LEU} {Supply} ({Enrichment}, {De}-conversion, {Fuel} {Fab} \& {Transportation})},
	url = {https://gain.inl.gov/HALEU_Webinar_Presentations/12-Nagley,BWXT-28Apr2020.pdf},
	language = {en},
	author = {Nagley, Scott},
	month = apr,
	year = {2020},
	note = {Place: GAIN/NEI/EPRI Webinar},
	file = {Nagley - (Enrichment, De-conversion, Fuel Fab & Transportat.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\225HTNUB\\Nagley - (Enrichment, De-conversion, Fuel Fab & Transportat.pdf:application/pdf},
}

@techreport{nuclear_energy_institute_establishing_2022,
	title = {Establishing a {HALEU} {Infrastructure} for {Advanced} {Reactors}},
	url = {https://www.nei.org/resources/reports-briefs/establishing-a-haleu-infrastructure-for-advanced-r},
	abstract = {Establishing a High Assay Low Enriched Uranium Infrastructure for Advanced Reactors},
	language = {en},
	urldate = {2022-01-26},
	institution = {Nuclear Energy Institute},
	author = {{Nuclear Energy Institute}},
	month = jan,
	year = {2022},
	file = {NEI-White-Paper-Establishing-a-High-Assay-Low-Enriched-Uranium-Infrastructure-for-Advanced-Reactors-Jan-2022.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\GWDSAS4T\\7LEVLF3H.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\DK7VRLC3\\establishing-a-haleu-infrastructure-for-advanced-r.html:text/html},
}

@inproceedings{celikten_effects_2021,
	address = {Washington D.C.},
	title = {The {Effects} of {Impurities} in {Down}-{Blending} {Highly} {Enriched} {Uranium} on the {Reactor} {Neutronics} and {Cycle} {Length}},
	volume = {125},
	url = {https://epubs.ans.org/?a=50496&_ga=2.168282849.1300862486.1643044250-1896939585.1615568796},
	urldate = {2022-01-26},
	booktitle = {Transactions of the {American} {Nuclear} {Soceity} {Winter} {Meeting}},
	author = {Celikten, Osman S. and Sahin, Dagistan},
	month = dec,
	year = {2021},
	pages = {165--167},
	file = {ANS / Digital Nuclear Library / Transactions / Volume 125 / Number 1 / Pages 165-167:C\:\\Users\\abachmann\\Zotero\\storage\\LRM4UCKE\\epubs.ans.org.html:text/html;Celikten and Sahin - 2021 - The Effects of Impurities in Down-Blending Highly .pdf:C\:\\Users\\abachmann\\Zotero\\storage\\QKEEGG6N\\TMPAEA8B.pdf:application/pdf},
}

@techreport{wigeland_identification_2011,
	title = {Identification, {Description}, and {Characterization} of {Existing} and {Alternative} {Nuclear} {Energy} {Systems}},
	author = {Wigeland, R and Dixon, Brent and Gehin, J.},
	month = may,
	year = {2011},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\JJXFTUA3\\Wigeland and Dixon - 2022 - Identification, Description, and Characterization .pdf:application/pdf},
}

@article{betzler_molten_2017,
	title = {Molten salt reactor neutronics and fuel cycle modeling and simulation with {SCALE}},
	volume = {101},
	issn = {03064549},
	url = {https://linkinghub.elsevier.com/retrieve/pii/S0306454916309185},
	doi = {10.1016/j.anucene.2016.11.040},
	abstract = {Current interest in advanced nuclear energy and molten salt reactor (MSR) concepts has enhanced interest in building the tools necessary to analyze these systems. A Python script known as ChemTriton has been developed to simulate equilibrium MSR fuel cycle performance by modeling the changing isotopic composition of an irradiated fuel salt using SCALE for neutron transport and depletion calculations. Improved capabilities in ChemTriton include a generic geometry capable of modeling multi-zone and multi-fluid systems, enhanced time-dependent feed and separations, and a critical concentration search. Although more generally applicable, the capabilities developed to date are illustrated in this paper in three applied problems: (1) simulating the startup of a thorium-based MSR fuel cycle (a likely scenario requires the first of these MSRs to be started without available 233U); (2) determining the effect of the removal of different fission products on MSR operations; and (3) obtaining the equilibrium concentration of a mixed-oxide light-water reactor fuel in a two-stage fuel cycle with a sodium fast reactor. The third problem is chosen to demonstrate versatility in an application to analyze the fuel cycle of a non-MSR system. In the first application, the initial fuel salt compositions fueled with different sources of fissile material are made feasible after (1) removing the associated nonfissile actinides after much of the This manuscript has been authored by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan ).},
	language = {en},
	urldate = {2022-01-17},
	journal = {Annals of Nuclear Energy},
	author = {Betzler, Benjamin R. and Powers, Jeffrey J. and Worrall, Andrew},
	month = mar,
	year = {2017},
	pages = {489--503},
	file = {Betzler et al. - 2017 - Molten salt reactor neutronics and fuel cycle mode.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\REJ62SB9\\Betzler et al. - 2017 - Molten salt reactor neutronics and fuel cycle mode.pdf:application/pdf},
}

@misc{nuclear_energy_institute_initial_2021,
	title = {Initial {License} {Renewal} {Application} {Updates} for {U}.{S}. {Nuclear} {Power} {Plants}},
	url = {https://www.nei.org/resources/statistics/us-nuclear-license-renewal-filings},
	abstract = {Status of license renewals for U.S. nuclear reactors, including applications under review and applications anticipated.},
	language = {en},
	urldate = {2022-01-04},
	author = {{Nuclear Energy Institute}},
	month = may,
	year = {2021},
	note = {Publication Title: Nuclear Energy Institute},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\J2G2RVZ5\\us-nuclear-license-renewal-filings.html:text/html},
}

@misc{nuclear_energy_institute_second_2021,
	title = {Second {License} {Renewal} {Filings} {For} {U}.{S}. {Nuclear} {Power} {Plants}},
	url = {https://www.nei.org/resources/statistics/second-license-renewal-filings-for-u-s-nuclea},
	abstract = {Status of subsequent license renewals for U.S. nuclear reactors, including applications under review and applications anticipated.},
	language = {en},
	urldate = {2022-01-04},
	author = {{Nuclear Energy Institute}},
	month = jun,
	year = {2021},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\ZMCFGNE4\\second-license-renewal-filings-for-u-s-nuclea.html:text/html},
}

@misc{noauthor_table_2021,
	title = {Table 2. {Nuclear} power plant data as of {December} 31, 2017},
	url = {https://www.eia.gov/nuclear/spent_fuel/ussnftab2.php},
	urldate = {2022-01-04},
	month = mar,
	year = {2021},
	note = {Publication Title: U.S. Energy Information Administration},
	file = {Table 2. Nuclear power plant data as of December 31, 2017:C\:\\Users\\abachmann\\Zotero\\storage\\CIZHD5U8\\ussnftab2.html:text/html},
}

@incollection{del_cul_advanced_2010,
	address = {San Francisco, CA},
	series = {{NEA}},
	title = {Advanced head-end for the treatment of used {LWR} fuel},
	isbn = {978-92-64-99174-3},
	shorttitle = {Actinide and {Fission} {Product} {Partitioning} and {Transmutation}},
	url = {https://www.oecd-ilibrary.org/nuclear-energy/actinide-and-fission-product-partitioning-and-transmutation_9789264991743-en},
	abstract = {The voloxidation process was initially developed as a dry head-end method for removing tritium from spent uranium–plutonium reactor fuel prior to aqueous processing. Standard voloxidation of UO2-based fuels typically operates at temperatures between 500 and 600°C. This process converts the fuel into a fine U3O8 powder that can be easily separated from the cladding and completely releases tritium as tritiated water. A voloxidation process is being developed using these novel oxidising atmospheres: nitrogen dioxide, ozone and mixtures of the two. Un-irradiated pressurised water reactor uranium pellets and simulated fuel containing caesium iodide were used as surrogates. Treatment at significantly lower temperatures using a mixture of NO2/O2 or NO2/O3 produced a fine red powder of UO3 and released all the iodine (as I2) from the simulated fuel. This powder – containing the uranium as UO3, transuranium actinides and non-volatile fission product oxides – is readily soluble in dilute acid. For subsequent aqueous-based separations, these potential improvements can eliminate the prolonged dissolution step and mitigate the presence of iodine in processes downstream of voloxidation, thereby simplifying off-gas treatment. Both of these advantages should result in cost reductions. The fine UO3 powder separated from the cladding is also an excellent initial product for non-aqueous processing methods such as electrochemical separation in molten salts; halide volatility; DUPIC-like processes; supercritical CO2 dissolution; aqueous alkaline separations; and hybrid processes (for example, dry chlorination followed by aqueous washing)},
	language = {en},
	number = {6996},
	urldate = {2021-12-06},
	booktitle = {Actinide and {Fission} {Product} {Partitioning} and {Transmutation}: {Eleventh} {Information} {Exchange} {Meeting}},
	publisher = {OECD},
	author = {Del Cul, G. D. and Spencer, B.B. and Hunt, R.D. and Jubin, R.T. and Collins, E.D.},
	month = nov,
	year = {2010},
	doi = {10.1787/9789264991743-en},
	pages = {265--268},
	file = {OECD - 2012 - Actinide and Fission Product Partitioning and Tran.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\TMNQVGDP\\3YYS6G3R.pdf:application/pdf},
}

@article{bachmann_enrichment_2021,
	title = {Enrichment dynamics for advanced reactor {HALEU} support},
	volume = {7},
	copyright = {© A. M. Bachmann et al., Published by EDP Sciences, 2021},
	issn = {2491-9292},
	url = {https://www.epj-n.org/articles/epjn/abs/2021/01/epjn210024/epjn210024.html},
	doi = {10.1051/epjn/2021021},
	abstract = {Transitioning to High Assay Low Enriched Uranium-fueled reactors will alter the material requirements of the current nuclear fuel cycle, in terms of the mass of enriched uranium and Separative Work Unit capacity. This work simulates multiple fuel cycle scenarios using Cyclus to compare how the type of the advanced reactor deployed and the energy growth demand affect the material requirements of the transition to High Assay Low Enriched Uranium-fueled reactors. Fuel cycle scenarios considered include the current fleet of Light Water Reactors in the U.S. as well as a no-growth and a 1\% growth transition to either the Ultra Safe Nuclear Corporation Micro Modular Reactor or the X-energy Xe-100 reactor from the current fleet of U.S. Light Water Reactors. This work explored parameters of interest including the number of advanced reactors deployed, the mass of enriched uranium sent to the reactors, and the Separative Work Unit capacity required to enrich natural uranium for the reactors. Deploying Micro Modular Reactors requires a higher average mass and Separative Work Unit capacity than deploying Xe-100 reactors, and a lower enriched uranium mass and a higher Separative Work Unity capacity than required to fuel Light Water Reactors before the transition. Fueling Xe-100 reactors requires less enriched uranium and Separative Work Unit capacity than fueling Light Water Reactors before the transition.},
	language = {en},
	urldate = {2021-12-02},
	journal = {EPJ Nuclear Sciences \& Technologies},
	author = {Bachmann, Amanda M. and Fairhurst-Agosta, Roberto and Richter, Zoë and Ryan, Nathan and Munk, Madicken},
	year = {2021},
	pages = {22},
	annote = {Publisher: EDP Sciences},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\GWNP7M4R\\Bachmann et al. - 2021 - Enrichment dynamics for advanced reactor HALEU sup.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\IR7RAL7F\\epjn210024.html:text/html},
}

@inproceedings{yacout_dynamic_2004,
	address = {Chicago, IL},
	title = {Dynamic {Analysis} of the {AFCI} {Scenarios}},
	language = {en},
	booktitle = {{PHYSOR} 2004 -{The} {Physics} of {Fuel} {Cycles} and {Advanced} {Nuclear} {Systems}: {Global} {Developments}},
	publisher = {American Nuclear Society},
	author = {Yacout, A M and Hill, R N and Herring, J S},
	month = apr,
	year = {2004},
	pages = {10},
	file = {Yacout et al. - 2000 - Dynamic Analysis of the AFCI Scenarios.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\9BX2Z4TA\\XQIDBWV2.pdf:application/pdf},
}

@inproceedings{sunny_transition_2015,
	address = {Paris, France},
	title = {Transition {Analysis} of {Promising} {U}.{S}. {Future} {Fuel} {Cycles} {Using} {ORION}},
	abstract = {The US Department of Energy Office of Fuel Cycle Technologies performed an evaluation and screening (E\&S) study of nuclear fuel cycle options to help prioritize future research and development decisions. Previous work for this E\&S study focused on establishing equilibrium conditionsfor analysis examples of40 nuclearfuel cycle evaluation groups (EGs) and evaluating their performance according to a set of 22 standardized metrics. Following the E\&S study, additional studies are being conducted to assess transitioningfrom the current USfuel cycle to future fuel cycle options identified by the E\&S study as being most promising. These studies help inform decisions on how to effectively achieve full transition, estimate the length of time needed to undergo transition from the current fuel cycle, and evaluate performance of nuclear systems and facilities in place during the transition. These studies also help identify any barriers to achieve transition. Oak Ridge National Laboratory (ORNL) Fuel Cycle Options Campaign team used ORION to analyze the transition pathway from the existing US nuclear fuel cycle—the once-through use of low-enriched-uranium (LEU) fuel in thermal-spectrum light water reactors (LWRs) —to a new fuel cycle with continuous recycling ofplutonium and uranium in sodium fast reactors (SFRs). This paper discusses the analysis of the transition from an LWR to an SFR fleet using ORION, highlights the role of lifetime extensions of existing LWRs to aid transition, and discusses how a slight delay in SFR deployment can actually reduce the time to achieve an equilibrium fuel cycle.},
	language = {en},
	booktitle = {Proceedings of {Global} 2015},
	author = {Sunny, E and Worrall, A and Peterson, J and Powers, J and Gehin, J and Gregg, R},
	month = sep,
	year = {2015},
	pages = {10},
	file = {Sunny et al. - 2015 - Transition Analysis of Promising U.S. Future Fuel .pdf:C\:\\Users\\abachmann\\Zotero\\storage\\P98QMSNW\\MRNHNYNC.pdf:application/pdf},
}

@article{hernandez_potential_2020,
	title = {Potential fuel cycle performance of floating small modular light water reactors of {Russian} origin},
	volume = {144},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S030645492030253X},
	doi = {10.1016/j.anucene.2020.107555},
	abstract = {We examine the potential fuel cycle performance of high assay low-enriched uranium fueled small light water reactors by considering several floating small reactor concepts of Russian origin with 235U enrichment at 10\%, 15\%, and 19.7\%. These enrichments are generic but representative of the reactor concepts being considered. The small reactor concepts were considered parametrically at two different power densities and neutron leakage fractions. The analysis was performed for the U.S. Department of Energy Office of Nuclear Energy using the evaluation metrics from the Evaluation and Screening (E\&S) Study. The reference reactor system in a once-through fuel cycle with an enrichment greater than 5\%, but less than 20\%, in the E\&S study is a graphite-moderated modular high temperature gas-cooled reactor (mHTGR). The neutron spectrum of an mHTGR is very different from these Russian floating small reactor concepts, which is why this analysis was conducted. The fuel cycle analysis indicates that increasing core leakage negatively impacts the natural resource requirements as well as the spent nuclear fuel and high-level waste radioactivity normalized to a giga-watt electric year (GWe-yr) basis. Further, we found that the 235U enrichment of the fuel and the rated core power density have limited fuel cycle performance impacts. One impact is the slightly higher discharge burnup of the de-rated power cases resulting in different spent nuclear fuel and high-level waste radioactivity at 100 and 100,000 years after fuel discharge. The most significant result from the study is the observation that all the enrichment and power density cases resulted in decreased radioactivity at 100,000 years relative to the reference mHTGR example case with 15.5\%-enrichment from the E\&S study.},
	language = {en},
	urldate = {2020-09-15},
	journal = {Annals of Nuclear Energy},
	author = {Hernandez, Richard and Brown, Nicholas R.},
	month = sep,
	year = {2020},
	keywords = {Fuel cycle performance, High assay low-enriched uranium, Micro reactors, Small modular reactors},
	pages = {107555},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\ZMVQGNR8\\GLTXU8XJ.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\GLUPB3N5\\S030645492030253X.html:text/html},
}

@techreport{nuclear_energy_institute_addressing_2018,
	type = {Technical {Report}},
	title = {Addressing the {Challenges} with {Establishing} the {Infrastructure} for the front-end of the {Fuel} {Cycle} for {Advanced} {Reactors}.},
	url = {https://www.nei.org/resources/reports-briefs/infrastructure-for-the-front-end-fuel-cycle},
	language = {en},
	author = {{Nuclear Energy Institute}},
	month = jan,
	year = {2018},
	pages = {35},
	file = {Hussain - NEI White Paper Addressing the Challenges with Es.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\GVZ777ZS\\GQIKX3B4.pdf:application/pdf},
}

@article{burns_reactor_2020,
	title = {Reactor and fuel cycle performance of light water reactor fuel with {235U} enrichments above 5\%},
	volume = {142},
	issn = {0306-4549},
	url = {https://www.sciencedirect.com/science/article/pii/S0306454920301213},
	doi = {10.1016/j.anucene.2020.107423},
	abstract = {Recent advances in nuclear fuel materials research, particularly on the topic of accident-tolerant fuels, have brought up potential opportunities for expanding the operating envelope of existing light water reactors. As many of the performance improvements offered by these technologies may be most fully realized by increasing fuel enrichment beyond the standard 5\% limit, this paper examines the potential reactor performance and fuel cycle performance of low-enriched uranium oxide fueled light water reactors by generically considering pressurized water reactors with 235U enrichment from 5 to 7\%. Advanced cladding, including accident-tolerant cladding, has the potential to increase fuel burnup limits related to hydrogen in the cladding that coincide with those limits associated with end-of-life reactivity. Therefore, higher enrichment will be necessary in order to realize the higher fuel burnups. This work includes evaluation of the fuel cycle length, discharge burnup, reactivity coefficients, and fuel cycle performance, including radioactive waste and environmental impact metrics per unit energy generated. The analysis was performed using the evaluation metrics from the US Department of Energy Office of Nuclear Energy Fuel Cycle Evaluation and Screening Study. The reactor performance and safety analysis show that enrichments between 5 and 7\% would have similar fuel temperature and moderator temperature coefficients. However, the soluble boron coefficient would decrease in magnitude, requiring more corrosive boric acid in the coolant or other methods of reactivity control during the fuel cycle. At these higher enrichments the maximum burnup at the rim of the fuel pellet would increase by almost a factor of two, which is expected to impact the formation of high-burnup structure in the fuel and the corresponding thermo-mechanical fuel properties. The fuel cycle performance assessment shows that increasing enrichment reduces the quantity of high-level waste disposed per unit energy generated, but it increases the natural resource requirements normalized to a gigawatt-electricity-per-year basis. Another impact is the slightly higher discharge burnup, resulting in somewhat different activity levels of the spent nuclear fuel and high-level waste radioactivity at 100 and 100,000 years after fuel discharge. The environmental impacts—including land use, water use, carbon emission, and radiological exposure—are of the same magnitude per unit energy generated. However, the impacts are distributed differently. Less than 5\% enrichment has marginally more impact on the back-end of the fuel cycle, and greater than 5\% enrichment has marginally more impact on the front-end of the fuel cycle. Ultimately, no neutronic or reactor safety hindrances to employing light water reactor fuel with enrichments greater than 5\% are identified; given the achievable reactor performance benefits with advanced fuels, further practical exploration of increased enrichment fuel is recommended.},
	language = {en},
	urldate = {2021-04-28},
	journal = {Annals of Nuclear Energy},
	author = {Burns, Joseph R. and Hernandez, Richard and Terrani, Kurt A. and Nelson, Andrew T. and Brown, Nicholas R.},
	month = jul,
	year = {2020},
	keywords = {Fuel cycle performance, High assay low-enriched uranium, Light water reactors, Small reactors},
	pages = {107423},
	annote = {JC0008},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\YCURJ347\\GBVWKXCR.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\WGL63XXK\\S0306454920301213.html:text/html},
}

@misc{noauthor_where_nodate,
	title = {Where our uranium comes from - {U}.{S}. {Energy} {Information} {Administration} ({EIA})},
	url = {https://www.eia.gov/energyexplained/nuclear/where-our-uranium-comes-from.php},
	urldate = {2021-02-01},
	file = {Where our uranium comes from - U.S. Energy Information Administration (EIA):C\:\\Users\\abachmann\\Zotero\\storage\\TYKPXJJF\\where-our-uranium-comes-from.html:text/html},
}

@book{cacuci_handbook_2010,
	address = {New York},
	title = {Handbook of nuclear engineering},
	volume = {4: Reactors of Generations III and IV},
	isbn = {978-0-387-98149-9},
	language = {eng},
	publisher = {Springer},
	editor = {Cacuci, Dan Gabriel},
	year = {2010},
	keywords = {Nuclear engineering, Electronic books, etc, Handbooks, manuals},
}

@book{todreas_nuclear_2012,
	address = {Boca Raton, FL},
	edition = {2nd},
	title = {Nuclear systems},
	isbn = {978-1-4398-0887-0},
	language = {eng},
	publisher = {Taylor \& Francis},
	author = {Todreas, Neil E.},
	year = {2012},
	keywords = {Thermodynamics, Nuclear reactors, Thermal hydraulics, Fluid dynamics, Heat, Nuclear power plants, Transmission},
}

@techreport{noauthor_power_1989,
	address = {Vienna},
	type = {Technical {Report}},
	title = {Power {Reactor} {Information} {System} ({PRIS}): {Reference} and {On}-line {Access} {Manual}},
	url = {https://www.iaea.org/publications/762/power-reactor-information-system-pris-reference-and-on-line-access-manual},
	institution = {INTERNATIONAL ATOMIC ENERGY AGENCY},
	year = {1989},
}

@techreport{wieselquist_scale_2020,
	address = {Oak Ridge, TN},
	type = {Code {Manual}},
	title = {{SCALE} {Code} {System}},
	url = {https://www.ornl.gov/file/scale-62-manual/display},
	number = {ORNL/TM-2005/39},
	institution = {Oak Ridge National Laboratory},
	author = {Wieselquist, W.A. and Lefebvre, R. A. and Jessee, M. A.},
	month = apr,
	year = {2020},
}

@techreport{wigeland_nuclear_2014,
	title = {Nuclear {Fuel} {Cycle} {Evaluation} and {Screening} – {Final} {Report}},
	url = {https://fuelcycleevaluation.inl.gov/SitePages/Home.aspx},
	language = {en},
	number = {INL/EXT-14-21465},
	author = {Wigeland, R and Taiwo, T and Ludewig, H and Todosow, M and Halsey, W and Gehin, J and Jubin, R and Buelt, J and Stockinger, S and Jenni, K},
	month = oct,
	year = {2014},
	note = {Publication Title: Final Report},
	pages = {51},
	file = {Wigeland et al. - 2014 - Nuclear Fuel Cycle Evaluation and Screening – Fina.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\WBMESI7Y\\QMWPIXKM.pdf:application/pdf},
}

@techreport{vaden_isotopic_2018,
	title = {Isotopic {Characterization} of {HALEU} from {EBR}-{II} {Driver} {Fuel} {Processing}},
	url = {http://www.osti.gov/servlets/purl/1484450/},
	language = {en},
	number = {INL/EXT–18-51906-Rev000, 1484450},
	urldate = {2020-09-06},
	author = {Vaden, DeeEarl},
	month = nov,
	year = {2018},
	doi = {10.2172/1484450},
	pages = {INL/EXT--18--51906--Rev000, 1484450},
	file = {JAA7IWAG.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\UMWNKTUJ\\JAA7IWAG.pdf:application/pdf},
}

@techreport{patterson_haleu_2019,
	title = {{HALEU} {Decontamination} {Investigations} for {EBR}-{II} {Recovered} {Uranium}. {HALEU} {Drip} {Casting} {Results} in the {Fuel} {Conditioning} {Facility} {Cathode} {Processor}},
	url = {https://www.osti.gov/biblio/1503291},
	abstract = {The U.S. Department of Energy's Office of Scientific and Technical Information},
	language = {English},
	number = {INL/EXT-19-53191-Rev000},
	urldate = {2020-09-06},
	institution = {Idaho National Lab. (INL), Idaho Falls, ID (United States)},
	author = {Patterson, Michael N. (ORCID:0000000182452323) and Westphal, Brian R. and Tolman, David D. and Price, J. C.},
	month = mar,
	year = {2019},
	doi = {10.2172/1503291},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\MM2VFY9H\\RYGURJ3R.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\HNV2BX2N\\1503291.html:text/html},
}

@article{chee_demand-driven_2020,
	title = {Demand-{Driven} {Deployment} {Capabilities} in {Cyclus}, a {Fuel} {Cycle} {Simulator}},
	volume = {0},
	issn = {0029-5450},
	url = {https://doi.org/10.1080/00295450.2020.1753444},
	doi = {10.1080/00295450.2020.1753444},
	abstract = {The present U.S. nuclear fuel cycle faces challenges that hinder the expansion of nuclear energy technology. The U.S. Department of Energy identified four nuclear fuel cycle options that make nuclear energy technology more desirable. Successfully analyzing the transitions from the current fuel cycle to these promising fuel cycles requires a nuclear fuel cycle simulator that can predictively and automatically deploy fuel cycle facilities to meet user-defined power demand. This work introduces and demonstrates the demand-driven deployment capabilities in Cyclus, an open-source nuclear fuel cycle simulator framework. User-controlled capabilities such as time-series forecasting algorithms, supply buffers, and facility preferences were introduced to give users tools to minimize power undersupply in a transition scenario simulation. The demand-driven deployment capabilities are referred to as d3ploy. We demonstrate the capability of d3ploy to predict future commodities’ supply and demand, and automatically deploy fuel cycle facilities to meet the predicted demand in four transition scenarios. Using d3ploy to set up transition scenarios saves the user simulation setup time compared to previous efforts that required a user to manually calculate and use trial and error to set up the deployment scheme for the supporting fuel cycle facilities.},
	number = {0},
	urldate = {2020-08-07},
	journal = {Nuclear Technology},
	author = {Chee, Gwendolyn J. and Agosta, Roberto E. Fairhurst and Bae, Jin Whan and Flanagan, Robert R. and Scopatz, Anthony M. and Huff, Kathryn D.},
	month = jul,
	year = {2020},
	keywords = {nuclear fuel cycle, Nuclear engineering, automated deployment, nuclear fuel cycle simulator, time-series forecasting},
	pages = {1--22},
	file = {Chee et al. - 2020 - Demand Driven Deployment Capabilities in Cyclus, a.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\J5T3ZE6E\\Chee et al. - 2020 - Demand Driven Deployment Capabilities in Cyclus, a.pdf:application/pdf;Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\KEWZRUJX\\G6HF87WZ.pdf:application/pdf},
}

@misc{mitchell_usnc_2020,
	title = {{USNC} {Micro} {Modular} {Reactor} – {Project} and {Fuel}},
	url = {https://gain.inl.gov/HALEU_Webinar_Presentations/33-Mitchell,Ultrasafe_Rev02-29apr2020.pdf},
	language = {en},
	urldate = {2020-06-26},
	author = {Mitchell, Mark},
	month = apr,
	year = {2020},
	note = {Place: Virtual Meeting
Type: Webinar},
	file = {Mitchell - 2020 - USNC Micro Modular Reactor – Project and Fuel.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\RVKMQL7T\\Mitchell - 2020 - USNC Micro Modular Reactor – Project and Fuel.pdf:application/pdf},
}

@misc{robinson_establishment_2020,
	title = {Establishment of a {HALEU} {Advanced} {Rx} {Strategic} {Reserve} ({Y}/{PM}-20-042)},
	url = {https://gain.inl.gov/HALEU_Webinar_Presentations/23-24-Robinson-Jollay,Y-12_Brief-29Apr2020.pdf},
	language = {en},
	urldate = {2020-06-20},
	author = {Robinson, R Chris and Jollay, Lloyd},
	month = apr,
	year = {2020},
	note = {Place: Virtual Meeting
Type: Webinar},
	file = {Robinson and Jollay - Establishment of a HALEU Advanced Rx Strategic Res.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\VIBMCUTA\\Robinson and Jollay - Establishment of a HALEU Advanced Rx Strategic Res.pdf:application/pdf},
}

@misc{griffith_overview_2020,
	title = {Overview of {NE}’s {High}-{Assay} {Low} {Enriched} {Uranium} ({HALEU}) {Program}},
	url = {https://gain.inl.gov/HALEU_Webinar_Presentations/02-Griffith,NE_HALEU_Program_Update-28Apr2020.pdf},
	abstract = {• Inform stakeholders on current challenges associated with HALEU - Understanding and estimating demand - Enrichment, conversion, and deconversion capabilities - Transportation - Legislative and regulatory issues • Discuss “division of labor”: where government and private roles connect • Inform DOE of steps we should tak},
	language = {en},
	urldate = {2020-06-20},
	author = {Griffith, Andy},
	month = apr,
	year = {2020},
	note = {Place: Virtual Meeting
Type: Webinar},
	file = {Griffith - Overview of NE’s High-Assay Low Enriched Uranium (.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\QQ6D9Y9C\\Griffith - Overview of NE’s High-Assay Low Enriched Uranium (.pdf:application/pdf},
}

@article{leppanen_serpent_2014,
	title = {The {Serpent} {Monte} {Carlo} code: {Status}, development and applications in 2013},
	volume = {82},
	issn = {0306-4549},
	shorttitle = {The {Serpent} {Monte} {Carlo} code},
	doi = {10.1016/j.anucene.2014.08.024},
	abstract = {The Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT Technical Research Centre of Finland since 2004, and is currently used in over 100 universities and research organizations around the world. This paper presents the brief history of the project, together with the currently available methods and capabilities and plans for future work. Typical user applications are introduced in the form of a summary review on Serpent-related publications over the past few years.},
	urldate = {2017-04-10},
	journal = {Annals of Nuclear Energy},
	author = {Leppanen, Jaakko and Pusa, Maria and Viitanen, Tuomas and Valtavirta, Ville and Kaltiaisenaho, Toni},
	month = aug,
	year = {2014},
	keywords = {Monte Carlo, Reactor physics, Burnup calculation, Homogenization},
	pages = {142--150},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\UGEZYP7N\\Leppänen et al. - 2015 - The Serpent Monte Carlo code Status, development .pdf:application/pdf;ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\F9BWV6ZF\\Leppänen et al. - 2015 - The Serpent Monte Carlo code Status, development .pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\8JVJKXSZ\\S0306454914004095.html:text/html;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\ARH425D3\\S0306454914004095.html:text/html},
}

@article{carlsen_cycamore_2014,
	title = {Cycamore v1.0.0},
	url = {http://figshare.com/articles/Cycamore_v1_0_0/1041829},
	doi = {http://figshare.com/articles/Cycamore_v1_0_0/1041829},
	abstract = {Additional module for Cyclus, the nuclear fuel cycle simulator developed at the University of Wisconsin - Madison, supporting the modeling of innovative fuel cycles.},
	urldate = {2014-06-03},
	journal = {Figshare},
	author = {Carlsen, Robert W. and Gidden, Matthew and Huff, Kathryn and Opotowsky, Arrielle C. and Rakhimov, Olzhas and Scopatz, Anthony M. and Wilson, Paul},
	month = jun,
	year = {2014},
	keywords = {agent-based simulation, Nuclear Fuel Cycle},
	annote = {http://figshare.com/articles/Cycamore\_v1\_0\_0/1041829},
	file = {cycamore_1.0.0:C\:\\Users\\abachmann\\Zotero\\storage\\YGGEKPQM\\Scopatz et al. - 2014 - Cycamore v1.0.0:application/octet-stream;Figshare Download:C\:\\Users\\abachmann\\Zotero\\storage\\37AH6SM4\\Scopatz et al. - 2014 - Cycamore v1.0.0:application/octet-stream;Figshare Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\X88PFR2D\\Scopatz et al. - 2014 - Cycamore v1.0.0.html:text/html;Full Text (HTML):C\:\\Users\\abachmann\\Zotero\\storage\\BUGLHBZK\\Scopatz et al. - 2014 - Cycamore v1.0.0.html:text/html},
}

@article{sobol_global_2001,
	series = {The {Second} {IMACS} {Seminar} on {Monte} {Carlo} {Methods}},
	title = {Global sensitivity indices for nonlinear mathematical models and their {Monte} {Carlo} estimates},
	volume = {55},
	issn = {0378-4754},
	url = {http://www.sciencedirect.com/science/article/pii/S0378475400002706},
	doi = {10.1016/S0378-4754(00)00270-6},
	abstract = {Global sensitivity indices for rather complex mathematical models can be efficiently computed by Monte Carlo (or quasi-Monte Carlo) methods. These indices are used for estimating the influence of individual variables or groups of variables on the model output.},
	language = {en},
	number = {1},
	urldate = {2019-11-27},
	journal = {Mathematics and Computers in Simulation},
	author = {Sobol, I. M},
	month = feb,
	year = {2001},
	keywords = {Monte Carlo method, Sensitivity analysis, Mathematical modelling, Quasi-Monte Carlo method},
	pages = {271--280},
	file = {ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\56AS6FVK\\S0378475400002706.html:text/html;Sobol′ - 2001 - Global sensitivity indices for nonlinear mathemati.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\6J76F2SC\\NK3C3HME.pdf:application/pdf},
}

@article{im_sensitivity_1993,
	title = {Sensitivity estimates for nonlinear mathematical models},
	volume = {1},
	number = {4},
	journal = {Math. Model. Comput. Exp},
	author = {IM, Sobol’},
	year = {1993},
	pages = {407--414},
}

@article{homma_importance_1996,
	title = {Importance measures in global sensitivity analysis of nonlinear models},
	volume = {52},
	number = {1},
	journal = {Reliability Engineering \& System Safety},
	author = {Homma, Toshimitsu and Saltelli, Andrea},
	year = {1996},
	pages = {1--17},
}

@misc{chee_arfcdcwrapper_2019,
	title = {arfc/dcwrapper : {Gwen}'s {MS} {Thesis} {Release}},
	shorttitle = {arfc/dcwrapper},
	abstract = {This version of dcwrapper was used to create the results in @gwenchee's MS Thesis. This release creates a doi for this version of the project.},
	urldate = {2017-08-31},
	publisher = {Advanced Reactors and Fuel Cycles Research Group},
	author = {Chee, Gwendolyn and Westphal, Gregory and Huff, Kathryn},
	year = {2019},
	doi = {10.5281/zenodo.3530964},
	note = {Published:  https://doi.org/10.5281/zenodo.3530964},
	file = {arfc/dcwrapper\: dcwrapper v1.0 | Zenodo:C\:\\Users\\abachmann\\Zotero\\storage\\Q8XISVI2\\3530964.html:text/html},
}

@mastersthesis{chee_sensitivity_2019,
	address = {Urbana, IL},
	title = {Sensitivity {Analysis} of {Nuclear} {Fuel} {Cycle} {Transitions}},
	copyright = {Copyright 2019 Gwendolyn Jin Yi Chee},
	url = {https://www.ideals.illinois.edu/handle/2142/106272},
	abstract = {The present United States nuclear fuel cycle faces challenges that hinder the expansion of nuclear energy technology. The U.S. Department of Energy identi ed four classes of nuclear fuel cycle options the U.S could transition to, which would overcome these challenges and make nuclear energy technology more desirable. The transitions have been modeled by various nuclear fuel cycle simulators. However, most fuel cycle simulators require the user to define a deployment scheme for all supporting facilities to avoid any supply chain gaps, which becomes tedious for complex transition scenarios. This thesis developed a capability in Cyclus, a nuclear fuel cycle simulator, to automatically deploy fuel cycle facilities to meet user-defined power demand. This new capability successfully deployed fuel cycle facilities in a transition scenario from the current light water reactor fleet to a closed fuel cycle with continuous recycling of transuranics in fast and thermal reactors. In reality, these transition scenarios inevitably diverge from the modeled scenario. This work coupled the nuclear fuel cycle simulator tools, Cyclus and DYMOND, with Dakota, a sensitivity analysis toolkit. This work conducted one-at-a-time, synergistic, and global sensitivity analysis with Cyclus-Dakota and DYMOND-Dakota, to understand the interdependence of input parameters on the transition performance from the current light water reactor eet to a closed fuel cycle in which transuranics are recycled to fuel mixed oxide fuel thermal reactors and sodium fast-cooled reactors. The global sensitivity analysis concluded that the transition year input parameter was the most influential to the final depleted uranium and total idle reactor capacity performance metrics, and the fleet share ratio and cooling time input parameters were the most influential to the final high level waste amount in the simulation. The one-at-a-time sensitivity analysis showed that varying transition year from 80 to 84 years increased the final depleted uranium amount by 1.13\% and reduced the total idle reactor capacity by 10.36\%. The one-at-a-time sensitivity analysis also showed that varying fleet share ratio (mixed oxide fuel light water reactor: sodium fast-cooled reactor) from 0:100 to 20:80 reduced the final high level waste amount by 2\%, and varying the used fuel cooling time from 0 to 8 years reduced the final high level waste amount by 4\%. Therefore, an optimized transition scenario that minimizes final high level waste amount, final depleted uranium amount, and total idle capacity must have a fleet share ratio of 20:80, used fuel cooling time of 8 years, and a transition year at 83 years. This work compared Cyclus-Dakota's and DYMOND-Dakota's sensitivity analysis capabilities and concluded that automated deployment of supporting fuel cycle facilities is crucial for conducting sensitivity analyses with nuclear fuel cycle simulators, to ensure that the simulation adapts to the new parameters by minimizing idle reactor capacity. The results demonstrated that time is saved if a comprehensive sensitivity analysis of a nuclear fuel cycle transition scenario begins with a global sensitivity analysis study to gain a general overview of the influential input variables for the performance metrics. Then, based on the global sensitivity analysis results, a reduced number of one-at-a-time and synergistic sensitivity analyses are conducted to determine quantitative trends and impacts of influential input variables on the performance metrics.},
	language = {English},
	school = {University of Illinois at Urbana-Champaign},
	author = {Chee, Gwendolyn J.},
	year = {2019},
	file = {gwen-ms-thesis-12-10.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\FPWBB5F8\\gwen-ms-thesis-12-10.pdf:application/pdf},
}

@techreport{hawari_development_2018,
	title = {Development and {Deployment} {Assessment} of a {Melt}-{Down} {Proof} {Modular} {Micro} {Reactor} ({MDP}-{MMR})},
	url = {http://www.osti.gov/servlets/purl/1431209/},
	language = {en},
	number = {14–6782, 1431209},
	urldate = {2019-08-01},
	institution = {North Carolina State University},
	author = {Hawari, Ayman I. and Venneri, Francesco},
	month = apr,
	year = {2018},
	doi = {10.2172/1431209},
	pages = {14--6782, 1431209},
	file = {Hawari and Venneri - 2018 - Development and Deployment Assessment of a Melt-Do.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\AWVFMAWJ\\FFYK2EDQ.pdf:application/pdf},
}

@mastersthesis{bae_fuel_2018,
	address = {Urbana, IL},
	title = {Fuel cycle transition simulation capabilities in {CYCLUS}},
	copyright = {Copyright 2018 Jin Whan Bae},
	url = {https://www.ideals.illinois.edu/handle/2142/102517},
	abstract = {Recent interest in advanced reactors and the following need for techno-economic transitions has increased the demand for tools necessary to model complex nuclear fuel cycles (NFCs) and advanced reactor technologies. This thesis demonstrates the capability of CYCLUS , the agent-based fuel cycle simulator, to model, simulate, and analyze real-life fuel cycle transition scenarios. I introduce new methods and tools that use various databases to model and simulate real-world nuclear fuel cycle transition scenarios involving advanced reactor technologies. The work in this thesis contains: (1) benchmarking Cyclus to other nuclear fuel cycle simulators (NFC simulators); (2) developing new methods and tools necessary for modeling and simulating real-world fuel cycle transition scenarios; (3) simulation of both domestic and international nuclear technology transitions. The methods and tools developed for such capabilities include: (1) modeling and simulating past and current nuclear fleets using historic nuclear reactor operations database; (2) modeling individual reactors and their operating history to calculate nuclear material inventory; (3) modeling Molten Salt Reactor (MSR) behavior in a large-scale fuel cycle simulation. Benchmark work shows that CYCLUS results coincide with results from other NFC simulators with minor differences due to modeling choices. Additionally, this thesis demonstrates the CYCLUS capability to effectively model and simulate real-life NFC transition scenarios that involve advanced reactor technologies such as MSRs.},
	language = {en},
	urldate = {2019-06-13},
	school = {University of Illinois at Urbana-Champaign},
	author = {Bae, Jin Whan},
	month = dec,
	year = {2018},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\B59UIDJK\\Bae - 2018 - Fuel cycle transition simulation capabilities in C.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\SIVL975R\\102517.html:text/html},
}

@article{huff_fundamental_2016,
	title = {Fundamental concepts in the {Cyclus} nuclear fuel cycle simulation framework},
	volume = {94},
	issn = {0965-9978},
	url = {http://www.sciencedirect.com/science/article/pii/S0965997816300229},
	doi = {10.1016/j.advengsoft.2016.01.014},
	abstract = {As nuclear power expands, technical, economic, political, and environmental analyses of nuclear fuel cycles by simulators increase in importance. To date, however, current tools are often fleet-based rather than discrete and restrictively licensed rather than open source. Each of these choices presents a challenge to modeling fidelity, generality, efficiency, robustness, and scientific transparency. The Cyclus nuclear fuel cycle simulator framework and its modeling ecosystem incorporate modern insights from simulation science and software architecture to solve these problems so that challenges in nuclear fuel cycle analysis can be better addressed. A summary of the Cyclus fuel cycle simulator framework and its modeling ecosystem are presented. Additionally, the implementation of each is discussed in the context of motivating challenges in nuclear fuel cycle simulation. Finally, the current capabilities of Cyclus are demonstrated for both open and closed fuel cycles.},
	language = {en},
	urldate = {2016-02-12},
	journal = {Advances in Engineering Software},
	author = {Huff, Kathryn D. and Gidden, Matthew J. and Carlsen, Robert W. and Flanagan, Robert R. and McGarry, Meghan B. and Opotowsky, Arrielle C. and Schneider, Erich A. and Scopatz, Anthony M. and Wilson, Paul P. H.},
	month = apr,
	year = {2016},
	keywords = {agent based modeling, Agent based modeling, and Science, Computer Science - Computational Engineering, Computer Science - Mathematical Software, Computer Science - Multiagent Systems, Computer Science - Software Engineering, D.2.13, D.2.4, Finance, I.6.7, I.6.8, nuclear engineering, Nuclear engineering, Nuclear fuel cycle, Object orientation, simulation, Simulation, Systems analysis},
	pages = {46--59},
	annote = {arXiv: 1509.03604},
	annote = {arXiv: 1509.03604},
	file = {arXiv\:1509.03604 PDF:C\:\\Users\\abachmann\\Zotero\\storage\\KZU34Q3F\\Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf;arXiv\:1509.03604 PDF:C\:\\Users\\abachmann\\Zotero\\storage\\ZF7WMBXD\\Huff et al. - 2015 - Fundamental Concepts in the Cyclus Fuel Cycle Simu.pdf:application/pdf;arXiv\:1509.03604 PDF:C\:\\Users\\abachmann\\Zotero\\storage\\PUNQ8PPP\\Huff et al. - 2015 - Fundamental Concepts in the Cyclus Fuel Cycle Simu.pdf:application/pdf;arXiv.org Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\K78UATU2\\1509.html:text/html;arXiv.org Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\VMC6JDQC\\1509.html:text/html;arXiv.org Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\PDLPJA4R\\1509.html:text/html;Fulltext:C\:\\Users\\abachmann\\Zotero\\storage\\NPFVNP5L\\Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf;fundamentals.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\Z9TM9M6H\\fundamentals.pdf:application/pdf;fundamentals.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\IWQCTGZN\\fundamentals.pdf:application/pdf;ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\GXFPHXCQ\\E7DK64AA.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\YT6ZQ84S\\S0965997816300229.html:text/html;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\VZ7J2IFQ\\S0965997816300229.html:text/html;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\HK6XTP6V\\S0965997816300229.html:text/html;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\BEENWBVK\\login.html:text/html;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\62FAZJDR\\S0965997816300229.html:text/html},
}

@article{widder_benefits_2010,
	title = {Benefits and concerns of a closed nuclear fuel cycle},
	volume = {2},
	url = {https://aip.scitation.org/doi/abs/10.1063/1.3506839},
	doi = {10.1063/1.3506839},
	abstract = {Nuclear power can play an important role in our energy future, helping to meet increasing electricity demand while at the same time decreasing carbon dioxide emissions. However, the nuclear fuel cycle in the United States today is unsustainable. The 1982 Nuclear Waste Policy Act establishes the U.S. Department of Energy as responsible for disposing of spent nuclear fuel (SNF) generated by commercial nuclear power plants operating in a “once-through” fuel cycle in a deep geologic repository located at Yucca Mountain, NV. However, unyielding political opposition to the Yucca Mountain site has hindered the commissioning process to the extent that the current administration has recently declared the site unsuitable. In light of this, the DOE is exploring other options, including closing the fuel cycle through reprocessing and recycling of spent nuclear fuel. The possibility of closing the fuel cycle is receiving special attention because of its ability to minimize the final high level waste package by separating and isolating the most long-lived components, as well as recovering additional energy value from the original fuel. Reprocessing and recycling of SNF can decrease the volume of waste stored by a factor of 4 and reduce the timeframe of storage from hundreds of thousands of years to thousands of years. Reprocessing and recycling technologies are, however, still very controversial because of the increased cost and proliferation risk reprocessing can present. Estimates of increases in the levelized cost of electricity with reprocessing range from about 10\% to 50\% due to large uncertainties in the financing, construction, and licensing of a new plant. Ultimately, the U.S. will need to compare each of these fuel cycle options with respect to sustainability, proliferation risk, commercial viability, waste management, and energy security to define the future of nuclear power.},
	number = {6},
	urldate = {2018-04-05},
	journal = {Journal of Renewable and Sustainable Energy},
	author = {Widder, Sarah},
	month = nov,
	year = {2010},
	pages = {062801},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\2DCCD3D5\\Widder - 2010 - Benefits and concerns of a closed nuclear fuel cyc.pdf:application/pdf;Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\5R59WD8L\\GPK5DXHP.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\YMYYKKYU\\1.html:text/html;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\L47LJ3J5\\1.html:text/html},
}

@article{poinssot_improving_2015,
	title = {Improving the nuclear energy sustainability by decreasing its environmental footprint. {Guidelines} from life cycle assessment simulations},
	issn = {0149-1970},
	url = {http://www.sciencedirect.com/science/article/pii/S0149197015300925},
	doi = {10.1016/j.pnucene.2015.10.012},
	abstract = {This paper describes the anticipated long-term evolutions of nuclear fuel cycles. The main driver for such an evolution is the need for improving the sustainability of global energy systems. Indeed, sustainability is becoming the international reference approach to reconciling the different fields of analysis, i.e. the technical performance, economic viability, environmental preservation and societal acceptance. While our societies have to face the issue of finding new energy models which help to mitigate climate change, global approaches are mandatory to select the relevant improvements for the different energy systems, including nuclear energy. In a first step, this paper focuses on the specific environmental footprint of nuclear energy and its position with regards the other energy sources. From this situation, this paper depicts the potential improvement to be studied in order to improve the overall environmental footprint.},
	urldate = {2015-12-05},
	journal = {Progress in Nuclear Energy},
	author = {Poinssot, Ch. and Bourg, S. and Boullis, B.},
	year = {2015},
	keywords = {Reprocessing, Nuclear Fuel Cycle, Sustainability, Actinides recycling, Back-end of the fuel cycle, Uranium resource},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\XXCHV9FX\\Poinssot et al. - Improving the nuclear energy sustainability by dec.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\9Z29MJYM\\Poinssot et al. - Improving the nuclear energy sustainability by dec.html:text/html},
}

@misc{khan_feasibility_2017,
	title = {Feasibility {Studies} on {Pyro}-{SFR} {Closed} {Fuel} {Cycle} and {Direct} {Disposal} of {Spent} {Nuclear} {Fuel} in {Line} with the {Latest} {National} {Policy} and {Strategy} of {Korea}},
	url = {https://www.hindawi.com/journals/stni/2017/1953256/},
	abstract = {With a view to providing supportive information for the decision-making on the direction of the future nuclear energy systems in Korea (i.e., direct disposal or recycling of spent nuclear fuel) to be made around 2020, quantitative studies on the spent nuclear fuel (SNF) including transuranic elements (TRUs) and a series of economic analyses were conducted. At first, the total isotopic inventory of TRUs in the SNF to be generated from all thirty-six units of nuclear power plants in operation or under planning is estimated based on the Korean government’s official plan for nuclear power development. Secondly, the optimized deployment strategies are proposed considering the minimum number of sodium cooled-fast reactors (SFRs) needed to transmute all TRUs. Finally, direct disposal and Pyro-SFR closed nuclear energy systems were compared using equilibrium economic model and considering reduction of TRUs and electricity generation as benefits. Probabilistic economic analysis shows that the assumed total generation cost for direct disposal and Pyro-SFR closed nuclear energy systems resides within the range of 13.60{\textbackslash}textasciitilde33.94 mills/kWh and 11.40{\textbackslash}textasciitilde25.91 mills/kWh, respectively. Dominant cost elements and the range of SFR overnight cost which guarantees the economic feasibility of the Pyro-SFR closed nuclear energy system over the direct disposal option were also identified through sensitivity analysis and break-even cost estimation.},
	language = {en},
	urldate = {2019-06-18},
	author = {Khan, Muhammad Minhaj and Lee, Jae Min and Cheong, Jae Hak and Whang, Joo Ho},
	year = {2017},
	doi = {10.1155/2017/1953256},
	note = {Publication Title: Science and Technology of Nuclear Installations
Type: Research article},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\7R3FVGT7\\Khan et al. - 2017 - Feasibility Studies on Pyro-SFR Closed Fuel Cycle .pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\L63SDC36\\1953256.html:text/html},
}

@techreport{noauthor_effects_2017,
	title = {The {Effects} of the {Uncertainty} of {Input} {Parameters} on {Nuclear} {Fuel} {Cycle} {Scenario} {Studies}},
	url = {https://www.oecd-nea.org/science/docs/2016/nsc-r2016-4.pdf},
	number = {NEA/NSC/R(2016)4},
	urldate = {2019-06-21},
	institution = {OECD, Nuclear Energy Agency},
	month = mar,
	year = {2017},
	file = {nsc-r2016-4.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\HFYE467D\\B8BLJ48U.pdf:application/pdf},
}

@inproceedings{gregg_analysis_2012,
	address = {Manchester, United Kingdom},
	title = {Analysis of the {UK} {Nuclear} {Fission} {Roadmap} using the {ORION} fuel cycle modelling code},
	url = {http://www.icheme.org/events/conferences/nuclear%20fuel%20cycle%20conference/ /media/2255BD59DEAC4D6D9C2C78032E995B5A.pdf},
	booktitle = {Proc of the {IChemE} nuclear fuel cycle conference, {Manchester}, {United} {Kingdom}},
	author = {Gregg, Robert and Grove, C.},
	year = {2012},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\FPE9AEGA\\Gregg and Grove - 2012 - Analysis of the UK Nuclear Fission Roadmap using t.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\NZZ7BCSL\\Gregg and Grove - 2012 - Analysis of the UK Nuclear Fission Roadmap using t.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\H44G6HYG\\Gregg and Grove - 2012 - Analysis of the UK Nuclear Fission Roadmap using t.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\AH83WAPL\\Gregg and Grove - 2012 - Analysis of the UK Nuclear Fission Roadmap using t.pdf:application/pdf},
}

@article{nishihara_impact_2008,
	title = {Impact of {Partitioning} and {Transmutation} on {LWR} {High}-{Level} {Waste} {Disposal}},
	volume = {45},
	issn = {0022-3131, 1881-1248},
	url = {http://www.tandfonline.com/doi/abs/10.1080/18811248.2008.9711418},
	doi = {10.1080/18811248.2008.9711418},
	abstract = {Partitioning and/or transmutation (PT) technology affects the disposal concept of high-level radioactive waste (HLW). We studied how cooling in the predisposal storage period may affect the design of the emplacement area in a repository for radioactive wastes produced by a light-water-reactor nuclear system that uses PT technology. Three different fuel cycle scenarios involving PT technology were analyzed: 1) partitioning process only (separation of some fission products), 2) transmutation process only (separation and transmutation of minor actinides), and 3) both partitioning and transmutation. The necessary predisposal storage periods for some predefined emplacement configurations were determined through transient thermal analysis, and the relation between the storage period and the emplacement area was obtained. For each scenario, we also estimated the storage capacity required for the dry storage of the heat-generating waste forms. The contributions of PT technology on the storage and disposal were discussed holistically, and we noted that the coupled introduction of partitioning and transmutation processes can bring an appreciable reduction in waste management size.},
	language = {en},
	number = {1},
	urldate = {2019-04-16},
	journal = {Journal of Nuclear Science and Technology},
	author = {Nishihara, Kenji and Nakayama, Shinichi and Morita, Yasuji and Oigawa, Hiroyuki and Iwasaki, Tomohiko},
	month = jan,
	year = {2008},
	pages = {84--97},
	file = {Nishihara et al. - 2008 - Impact of Partitioning and Transmutation on LWR Hi.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\T5JV5HRE\\Nishihara et al. - 2008 - Impact of Partitioning and Transmutation on LWR Hi.pdf:application/pdf},
}

@article{passerini_systematic_2014,
	title = {A {Systematic} {Approach} to {Nuclear} {Fuel} {Cycle} {Analysis} and {Optimization}},
	volume = {178},
	issn = {0029-5639},
	url = {https://doi.org/10.13182/NSE13-20},
	doi = {10.13182/NSE13-20},
	abstract = {Experience with modeling fuel cycle options reveals that the large amount of generated data makes it difficult to understand trade-offs among fuel cycle policies. This paper shows that numerical optimization can be used to better identify impacts of fuel cycle policies and condense the generated data against a few significant criteria. The once-through cycle is considered the baseline case, while advanced technologies with fuel recycling characterize the alternative fuel cycle options available in the future. The options include, among others, recycling the fissile materials from spent light water reactor fuel in fast reactors (FRs) as well as deployment of innovative recycling reactor technologies, such as the 235U initiated FRs. Additionally, a first-of-a-kind optimization scheme for the nuclear fuel cycle analysis is described. Optimization metrics of interest to different stakeholders in the fuel cycle (economics, fuel resource utilization, high-level waste, transuranic materials/proliferation management, and environmental impact) are utilized for two different optimization techniques: a linear one and a stochastic one. Stakeholder elicitation provided sets of relative weights for the identified metrics appropriate to each stakeholder group, which were then used to demonstrate feasibility of arrival at optimum fuel cycle configurations for recycling technologies. The stochastic optimization tool, based on a genetic algorithm, was used to identify noninferior solutions according to Pareto’s dominance approach to optimization. The main trade-off for fuel cycle optimization was found to be between emphasizing economics versus most of the other identified metrics.},
	number = {2},
	urldate = {2018-10-04},
	journal = {Nuclear Science and Engineering},
	author = {Passerini, Stefano and Kazimi, Mujid S. and Shwageraus, Eugene},
	month = oct,
	year = {2014},
	pages = {186--201},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\XKXEB9GX\\M7B6DPSB.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\4MU3SG5K\\NSE13-20.html:text/html},
}

@article{bae_standardized_2019,
	title = {Standardized verification of the {Cyclus} fuel cycle simulator},
	volume = {128},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454919300179},
	doi = {10.1016/j.anucene.2019.01.014},
	abstract = {Many nuclear fuel cycle simulators can analyze transitions from once-through to advanced nuclear fuel cycles. Verification studies compare various fuel cycle analysis tools to test agreement and identify sources of difference. A recent verification study, Feng et al. (2016) established transition scenario test case specifications and accordingly evaluated national laboratory nuclear fuel cycle simulators, DYMOND, VISION, ORION, and MARKAL. This work verifies the performance of Cyclus, the agent-based, open-source fuel cycle simulator, using the test case specifications in Feng et. al. In this work, Cyclus demonstrates agreement with the results from the previous verification study. Minor differences reflect intentional, detailed material tracking in the Cycamore reactor module. These results extend the example results in Feng et al. to further enable future verification of additional nuclear fuel cycle simulation tools.},
	urldate = {2019-01-25},
	journal = {Annals of Nuclear Energy},
	author = {Bae, Jin Whan and Peterson-Droogh, Joshua L. and Huff, Kathryn D.},
	month = jun,
	year = {2019},
	keywords = {agent based modeling, C, Finite elements, Hydrologic contaminant transport, MOOSE, Multiphysics, nuclear engineering, Nuclear fuel cycle, Object orientation, Parallel computing, Reactor physics, repository, Simulation, Systems analysis, Verification},
	pages = {288--291},
	file = {Bae et al. - 2018 - Standardized Verification of the Cyclus Fuel Cycle.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\I9LWWMLG\\Bae et al. - 2018 - Standardized Verification of the Cyclus Fuel Cycle.pdf:application/pdf;ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\6B7KDN6D\\UXQWH3GA.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\2I2IWESC\\S0306454919300179.html:text/html},
}

@article{feng_standardized_2016,
	title = {Standardized verification of fuel cycle modeling},
	volume = {94},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454916301098},
	doi = {10.1016/j.anucene.2016.03.002},
	abstract = {A nuclear fuel cycle systems modeling and code-to-code comparison effort was coordinated across multiple national laboratories to verify the tools needed to perform fuel cycle analyses of the transition from a once-through nuclear fuel cycle to a sustainable potential future fuel cycle. For this verification study, a simplified example transition scenario was developed to serve as a test case for the four systems codes involved (DYMOND, VISION, ORION, and MARKAL), each used by a different laboratory participant. In addition, all participants produced spreadsheet solutions for the test case to check all the mass flows and reactor/facility profiles on a year-by-year basis throughout the simulation period. The test case specifications describe a transition from the current US fleet of light water reactors to a future fleet of sodium-cooled fast reactors that continuously recycle transuranic elements as fuel. After several initial coordinated modeling and calculation attempts, it was revealed that most of the differences in code results were not due to different code algorithms or calculation approaches, but due to different interpretations of the input specifications among the analysts. Therefore, the specifications for the test case itself were iteratively updated to remove ambiguity and to help calibrate interpretations. In addition, a few corrections and modifications were made to the codes as well, which led to excellent agreement between all codes and spreadsheets for this test case. Although no fuel cycle transition analysis codes matched the spreadsheet results exactly, all remaining differences in the results were due to fundamental differences in code structure and/or were thoroughly explained. The specifications and example results are provided so that they can be used to verify additional codes in the future for such fuel cycle transition scenarios.},
	urldate = {2016-04-09},
	journal = {Annals of Nuclear Energy},
	author = {Feng, B. and Dixon, B. and Sunny, E. and Cuadra, A. and Jacobson, J. and Brown, N. R. and Powers, J. and Worrall, A. and Passerini, S. and Gregg, R.},
	month = aug,
	year = {2016},
	keywords = {DYMOND, MARKAL, ORION, VISION},
	pages = {300--312},
	file = {1-s2.0-S0306454916301098-main.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\L8ULABGR\\8WWHCWAD.pdf:application/pdf;Fulltext:C\:\\Users\\abachmann\\Zotero\\storage\\ADDSN88T\\Feng et al. - 2016 - Standardized verification of fuel cycle modeling.pdf:application/pdf;ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\23J5WA76\\Feng et al. - 2016 - Standardized verification of fuel cycle modeling.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\MJNXGKS9\\S0306454916301098.html:text/html;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\9EZJ5QQW\\S0306454916301098.html:text/html;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\85J6G9RY\\S0306454916301098.html:text/html;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\M48VDZVX\\S0306454916301098.html:text/html},
}

@article{jacobson_verifiable_2010,
	title = {Verifiable fuel cycle simulation model ({VISION}): a tool for analyzing nuclear fuel cycle futures},
	volume = {172},
	shorttitle = {Verifiable fuel cycle simulation model ({VISION})},
	number = {2},
	journal = {Nuclear Technology},
	author = {Jacobson, J. and Yacout, A. and Matthern, G. and Piet, S. and Shropshire, D. and Jeffers, R. and Schweitzer, T},
	month = nov,
	year = {2010},
	pages = {157--178},
	file = {nt_v172_n2_pp157-178.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\MYEZ6WSJ\\nt_v172_n2_pp157-178.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\DSVFQ2YW\\NT172-157.html:text/html},
}

@article{kim_selection_1999-1,
	title = {Selection of an optimal nuclear fuel cycle scenario by goal programming and the analytic hierarchy process},
	volume = {26},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454998000814},
	doi = {10.1016/S0306-4549(98)00081-4},
	abstract = {The front-end fuel cycle from mining to enrichment has reached maturity. Unlike the front-end fuel cycle, there are several pathways in the back-end fuel cycle. The long-term consequences of any decision for the back-end fuel cycle requires some sophisticated decision making tools. Various kinds of factors should be taken into consideration for the decision. In this study the Goal Programming Method in combination with the Analytic Hierarchy Process (AHP) is applied in the decision making process. For the treatment of tangible factors Goal Programming is used and for intangible factors AHP is used for quantification. A computer code was developed to combine both methods in the treatment of two different kinds of factors and to obtain a solution for the most optimal fuel cycle in Korea.},
	number = {5},
	urldate = {2017-10-15},
	journal = {Annals of Nuclear Energy},
	author = {Kim, Poong Oh and Lee, Kun Jai and Lee, Byong Whi},
	month = mar,
	year = {1999},
	pages = {449--460},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\ITV4AY8U\\Kim et al. - 1999 - Selection of an optimal nuclear fuel cycle scenari.pdf:application/pdf;ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\MX7KVU95\\Kim et al. - 1999 - Selection of an optimal nuclear fuel cycle scenari.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\FMW75IAN\\S0306454998000814.html:text/html;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\RATK2LG8\\S0306454998000814.html:text/html},
}

@inproceedings{yacout_modeling_2005,
	title = {Modeling the {Nuclear} {Fuel} {Cycle}},
	url = {http://www.inl.gov/technicalpublications/Documents/3169906.pdf},
	urldate = {2014-08-19},
	booktitle = {The 23rd {International} {Conference} of the {System} {Dynamics} {Society}," {Boston}},
	publisher = {Citeseer},
	author = {Yacout, A. M. and Jacobson, J. J. and Matthern, G. E. and Piet, S. J. and Moisseytsev, A.},
	year = {2005},
	file = {[PDF] from inl.gov:C\:\\Users\\abachmann\\Zotero\\storage\\4Z7VGFSP\\8GIVC4AA.pdf:application/pdf},
}

@incollection{seebregts_energyenvironmental_2002,
	series = {Operations {Research} {Proceedings} 2001},
	title = {Energy/{Environmental} {Modeling} with the {MARKAL} {Family} of {Models}},
	isbn = {978-3-540-43344-6 978-3-642-50282-8},
	url = {https://link.springer.com/chapter/10.1007/978-3-642-50282-8_10},
	abstract = {This article presents an overview and a flavour of almost two decades of MARKAL model developments and selected applications. The MARKAL family of models has been contributing to energy/environmental planning since the early J980’s. Under the auspices of the International Energy Agency’s (IEA) Energy Technology Systems Analysis Programme (ETSAP) the model started as a linear programming (LP) application focused strictly on the integrated assessment of energy systems. It was followed by a non-linear programming (NLP) formulation which combines the ‘bottom-up’ technology model with a ‘top-down’ simplified macro-economic model. In recent years, the family was enlarged by members to model material flows, to employ stochastic programming (SP) to address future uncertainties, to model endogenous technology learning using mixed integer programming (MIP) techniques, and to model multiple regions (NLP/LP).},
	language = {en},
	urldate = {2017-10-03},
	booktitle = {Operations {Research} {Proceedings} 2001},
	publisher = {Springer, Berlin, Heidelberg},
	author = {Seebregts, Ad J. and Goldstein, Gary A. and Smekens, Koen},
	year = {2002},
	doi = {10.1007/978-3-642-50282-8_10},
	pages = {75--82},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\CE6K57JH\\L34MCSSB.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\XUYNSGTR\\978-3-642-50282-8_10.html:text/html},
}

@inproceedings{betzler_fuel_2017,
	address = {Seoul, South Korea},
	title = {Fuel {Cycle} {Analysis} of {Thermal} and {Fast} {Spectrum}... - {Google} {Scholar}},
	url = {https://scholar.google.com/scholar?hl=en&as_sdt=0%2C14&q=Fuel+Cycle+Analysis+of+Thermal+and+Fast+Spectrum+Molten+Salt+Reactors&btnG=},
	abstract = {In support of the Fuel Cycle Options Campaign implemented by the US Department of Energy’s Office of Nuclear Energy, thermal and fast spectrum molten salt reactors (MSRs) were analyzed to assess performance of the reactor technology in various fuel cycles. These analyses include fuel cycles with (1) continuous recycle of U/Pu with new natural uranium fuel in fast critical reactors, (2) continuous recycle of U/Pu with new natural uranium fuel in both fast and thermal critical reactors, and (3) limited and continuous recycle of 233U/Th in thermal reactors. For each analysis, the evolution of the fuel salt was simulated for several years, and the fuel cycle metrics were calculated at the end of the simulation after equilibrium was achieved. Both thermal and fast spectrum MSRs performed well in replacing other technologies. Fuel cycle metrics highlight the impact of larger mass flow rates in MSRs due to their continuous treatment and separations of the fuel salt material. Liquid-fueled MSRs also provide a benefit in transition due to immediate availability of bred fissile material and low out-of-core time. Results from these analyses provide confidence that MSR technologies achieve adequate neutronic performance and may be used as an alternate reactor technology in the studied fuel cycles.},
	urldate = {2017-10-04},
	booktitle = {Proceedings of {GLOBAL} 2017},
	author = {Betzler, Benjamin R. and Powers, Jeffrey J. and Peterson-Droogh, Joshua L. and Worrall, Andrew},
	month = sep,
	year = {2017},
	file = {brb.fsmsr.v6.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\ZVVZCDBJ\\T3IR8CCQ.pdf:application/pdf;Fuel Cycle Analysis of Thermal and Fast Spectrum... - Google Scholar:C\:\\Users\\abachmann\\Zotero\\storage\\JXGGP9KI\\scholar.html:text/html},
}

@inproceedings{radel_effect_2007,
	address = {LaGrange Park, IL},
	title = {Effect of separation efficiency on repository loading values in fuel cycle scenario analysis codes},
	abstract = {Fuel cycle scenario analysis codes are valuable tools for investigating the effects of various decisions on the performance of the nuclear fuel cycle as a whole. Until recently, repository metrics in such codes were based on mass and were independent of the isotopic composition of the waste. A methodology has been developed for determining peak repository loading for an arbitrary set of isotopics based on the heat load restrictions and current geometry specifications for the Yucca Mountain repository. This model was implemented in the VISION fuel cycle scenario analysis code and is used here to study the effects of separation efficiencies on repository loading for various AFCI fuel cycle scenarios. Improved separations efficiencies are shown to have continuing technical benefit in fuel cycles that recycle Am and Cm, but a substantial benefit can be achieved with modest separation efficiencies. (authors)},
	booktitle = {American {Nuclear} {Society} {Transactions}},
	publisher = {American Nuclear Society},
	author = {Radel, Tracy E. and Wilson, Paul P.H. and Grady, R. M. and Bauer, Theodore H.},
	year = {2007},
	keywords = {Separation, Isotopes, Fuel cycle, Fuels, Loading, Nuclear Energy, nuclear engineering, Codes (standards), Codes (symbols), Fusion Reactions, Nuclear Fuel Reprocessing, Nuclear Fuels, Nuclear Physics, 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES, COMPUTERIZED SIMULATION, Efficiency, Geometry, Heating Load, Isomers, ISOTOPE RATIO, isotopes, Loads (forces), Modal Analysis, Performance, Photoacoustic Effect, Radioactive Wastes, Set Theory, specifications, Specifications, Yucca Mountain, Yucca Mountain Repository, EFFICIENCY, FUEL CYCLE, GEOMETRY, HEATING LOAD, PERFORMANCE, RADIOACTIVE WASTES, SPECIFICATIONS, YUCCA MOUNTAIN},
	annote = {Compilation and indexing terms, Copyright 2009 Elsevier Inc.},
	file = {2007_09_Radel_GLOBAL_Separations(177313).doc:C\:\\Users\\abachmann\\Zotero\\storage\\88STN9KK\\2007_09_Radel_GLOBAL_Separations(177313).doc:application/msword;2007_09_Radel_GLOBAL_Separations(177313).pdf:C\:\\Users\\abachmann\\Zotero\\storage\\PEJEMB3Y\\2007_09_Radel_GLOBAL_Separations(177313).pdf:application/pdf;Abstract_2007_Radel-Global07-SeparationsRepository.doc:C\:\\Users\\abachmann\\Zotero\\storage\\84MYUTNV\\Abstract_2007_Radel-Global07-SeparationsRepository.doc:application/msword;Abstract_2007_Radel-Global07-SeparationsRepository.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\GSS5UZUZ\\Abstract_2007_Radel-Global07-SeparationsRepository.pdf:application/pdf},
}

@article{hesketh_key_2017,
	title = {Key conclusions from {UK} strategic assessment studies of fast reactor fuel cycles},
	volume = {110},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454917301822},
	doi = {10.1016/j.anucene.2017.06.053},
	abstract = {The UK Government has made a commitment to reduce greenhouse gas emissions by 80\% from 1990 levels by 2050. Achieving this goal may demand a significant expansion of nuclear power and the Government has been exploring some very challenging scenarios with up to 75 GWe of nuclear capacity by 2050. Prior to establishing a national R\&D programme, the Government commissioned the National Nuclear Laboratory (NNL) and the Dalton Nuclear Institute (DNI) to lead a preliminary R\&D programme to fill in some gaps that have been identified. This initial R\&D included a programme of work on Strategic Assessment, which will look at possible future energy and nuclear deployment scenarios to identify the important constraints and limitations. The nuclear expansion scenarios envisage a new build programme based on a Light Water Reactor (LWR) fleet and in some of these scenarios the LWRs are at some point replaced by a fleet of fast reactors with recycle that would allow a self-sustaining fuel cycle independent of world uranium supplies. This paper focuses on the high level conclusions that arise from the fast reactor scenarios studied. The high level conclusions relate to constraints on timescales for expansion of nuclear capacity and technical specifications for fuel cycle and waste management plants. In particular the work illustrates how the driving factors for fast reactor deployment have changed since the UK was last involved seriously in fast reactor development work in the mid-1990s.},
	journal = {Annals of Nuclear Energy},
	author = {Hesketh, Kevin and Gregg, Robert and Butler, Gregg and Worrall, Andrew},
	month = dec,
	year = {2017},
	pages = {330--337},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\8K3SUHH3\\Hesketh et al. - 2017 - Key conclusions from UK strategic assessment studi.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\Z92KGFA3\\S0306454917301822.html:text/html},
}

@article{buckner_case_2016,
	title = {The case for nuclear fuel recycling},
	url = {http://www.ans.org/pubs/magazines/download/a_1011},
	journal = {Nuclear News},
	author = {Buckner, Melvin R. and Burchill, William E.},
	year = {2016},
	file = {[PDF] ans.org:C\:\\Users\\abachmann\\Zotero\\storage\\8KBXH57P\\Buckner and Burchill - 2016 - The case for nuclear fuel recycling.pdf:application/pdf},
}

@article{martin_symbiotic_2017,
	title = {Symbiotic equilibrium between {Sodium} {Fast} {Reactors} and {Pressurized} {Water} {Reactors} supplied with {MOX} fuel},
	volume = {103},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454916308076},
	doi = {10.1016/j.anucene.2017.01.041},
	abstract = {The symbiotic equilibrium between 1.51 GWe breeder SFR (Sodium Fast Reactors) and 1.6 GWe EPR™ (European Pressurized water Reactors) is studied. EPR™ are only supplied with MOX (Mixed OXide) fuel to avoid the use of natural uranium. The equilibrium is studied by considering the flows of plutonium. Its isotopic composition is here described by a single real number referred to as the Pu grade. Plutonium flows through both reactor types are characterized by using linear functions of the Pu grade in new fuels. These functions have been determined by fitting data from a former scenario study carried out with the COSI6 simulation software. Two different reprocessing strategies are considered. With joint reprocessing of all spent fuels, total and fissile plutonium flows balance for a unique fraction x of EPR™ in the fleet, equal to 0.2547. This x value is consistent with the results reported in the former scenario study mentioned above. When EPR™ spent fuels are used in priority to supply SFR (distinct reprocessing), x reaches 0.2582 at most. COSI6 simulations have been performed to further assess these results. The EPR™ fraction in the fleet at symbiotic equilibrium barely depends on the applied reprocessing strategy, so that the more flexible joint reprocessing constitutes the reference option in that case.},
	urldate = {2017-02-16},
	journal = {Annals of Nuclear Energy},
	author = {Martin, G. and Coquelet-Pascal, C.},
	month = may,
	year = {2017},
	keywords = {Nuclear energy, SFR, fast reactors, Plutonium, EPR™, Fuel reprocessing, Symbiotic nuclear systems, Thermal reactors},
	pages = {356--362},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\KXPTQKTZ\\Martin and Coquelet-Pascal - 2017 - Symbiotic equilibrium between Sodium Fast Reactors.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\XJTE2BD2\\S0306454916308076.html:text/html},
}

@article{brown_identification_2016,
	title = {Identification of fuel cycle simulator functionalities for analysis of transition to a new fuel cycle},
	volume = {96},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454916303383},
	doi = {10.1016/j.anucene.2016.05.027},
	abstract = {Dynamic fuel cycle simulation tools are intended to model holistic transient nuclear fuel cycle scenarios. As with all simulation tools, fuel cycle simulators require verification through unit tests, benchmark cases, and integral tests. Model validation is a vital aspect, as well. Although comparative studies have been performed, there is no comprehensive unit test and benchmark library for fuel cycle simulator tools. The objective of this paper is to identify some of the “must test” functionalities of a fuel cycle simulator tool within the context of specific problems of interest to the Fuel Cycle Options Campaign within the U.S. Department of Energy’s Office of Nuclear Energy (DOE-NE). This paper identifies the features needed to cover the range of promising fuel cycle options identified in the DOE-NE Fuel Cycle Evaluation and Screening and categorizes these features to facilitate prioritization. Features are categorized as essential functions, integrating features, and exemplary capabilities. A library of unit tests applicable to each of the essential functions should be developed as future work. An international dialog on the functionalities and standard test methods for fuel cycle simulator tools is encouraged.},
	urldate = {2016-09-23},
	journal = {Annals of Nuclear Energy},
	author = {Brown, Nicholas R. and Carlsen, Brett W. and Dixon, Brent W. and Feng, Bo and Greenberg, Harris R. and Hays, Ross D. and Passerini, Stefano and Todosow, Michael and Worrall, Andrew},
	month = oct,
	year = {2016},
	keywords = {Fuel cycle simulator, Transition analysis, Unit tests},
	pages = {88--95},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\9HVL6A3Z\\9H5GZ7QA.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\YYC9ITIF\\S0306454916303383.html:text/html;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\G4DDCBNF\\S0306454916303383.html:text/html},
}

@article{shmidt_modeling_2016,
	series = {{ATALANTE} 2016 {International} {Conference} on {Nuclear} {Chemistry} for {Sustainable} {Fuel} {Cycles}},
	title = {Modeling {Closed} {Nuclear} {Fuel} {Cycle} {Processes}},
	volume = {21},
	issn = {1876-6196},
	url = {http://www.sciencedirect.com/science/article/pii/S1876619616301127},
	doi = {10.1016/j.proche.2016.10.070},
	abstract = {Determination of optimal operating conditions for closed nuclear fuel cycle processes requires computer models that are used to evaluate and modify the design solution at earlier stages of technology development and the engineering and project documentation as more data from experimental research are obtained. The computational models being developed will significantly accelerate the design process, project commissioning as well as improve quality, performance and safety characteristics of the product.},
	urldate = {2016-12-08},
	journal = {Procedia Chemistry},
	author = {Shmidt, O. V. and Makeeva, I. R. and Liventsov, S. N.},
	year = {2016},
	keywords = {balance model, mathematical models of technological process, TP code, VIZART},
	pages = {503--508},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\NMXITBA3\\Shmidt et al. - 2016 - Modeling Closed Nuclear Fuel Cycle Processes.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\ZPEXKYYV\\S1876619616301127.html:text/html},
}

@article{gidden_methodology_2016,
	title = {A methodology for determining the dynamic exchange of resources in nuclear fuel cycle simulation},
	volume = {310},
	issn = {0029-5493},
	url = {https://www.sciencedirect.com/science/article/pii/S0029549316304101},
	doi = {10.1016/j.nucengdes.2016.10.029},
	abstract = {Simulation of the nuclear fuel cycle can be performed using a wide range of techniques and methodologies. Past efforts have focused on specific fuel cycles or reactor technologies. The CYCLUS fuel cycle simulator seeks to separate the design of the simulation from the fuel cycle or technologies of interest. In order to support this separation, a robust supply–demand communication and solution framework is required. Accordingly an agent-based supply-chain framework, the Dynamic Resource Exchange (DRE), has been designed implemented in CYCLUS. It supports the communication of complex resources, namely isotopic compositions of nuclear fuel, between fuel cycle facilities and their managers (e.g., institutions and regions). Instances of supply and demand are defined as an optimization problem and solved for each timestep. Importantly, the DRE allows each agent in the simulation to independently indicate preference for specific trading options in order to meet both physics requirements and satisfy constraints imposed by potential socio-political models. To display the variety of possible simulations that the DRE enables, example scenarios are formulated and described. Important features include key fuel-cycle facility outages, introduction of external recycled fuel sources (similar to the current mixed oxide (MOX) fuel fabrication facility in the United States), and nontrivial interactions between fuel cycles existing in different regions.},
	urldate = {2017-02-08},
	journal = {Nuclear Engineering and Design},
	author = {Gidden, Matthew J. and Wilson, Paul P. H.},
	month = dec,
	year = {2016},
	keywords = {Agent-based modeling, Nuclear Fuel Cycle, Optimization},
	pages = {378--394},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\SIEW6UKH\\PNNCUS7D.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\LTFHIDVP\\S0029549316304101.html:text/html},
}

@inproceedings{skutnik_cyborg_2016,
	address = {Las Vegas, Nevada, United States},
	series = {Fuel {Cycle} and {Waste} {Management}: {General}—{II}},
	title = {{CyBORG}: {An} {ORIGEN}-{Based} {Reactor} {Analysis} {Capability} for {Cyclus}},
	volume = {115},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Skutnik, Steven E. and Sly, Nicholas C. and Littell, Jennifer Lynn},
	month = nov,
	year = {2016},
	keywords = {C++, Code, Fuel cycle, Geniusv2, Global Evaluation of Nuclear Infrastructure Utilization Scenarios (GENIUS), Simulation, Technology},
	pages = {299--301},
	file = {Skutnik et al. - 2016 - CyBORG An ORIGEN-Based Reactor Analysis Capabilit.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\8R88JQVT\\43GGN9WD.pdf:application/pdf},
}

@article{huff_market_2014,
	title = {Market {Driven} {Transition} {Capability} for {Cyclus} {Simulations}},
	url = {http://figshare.com/articles/Market_Driven_Transition_Capability_for_Cyclus_Simulations/1134652},
	doi = {http://dx.doi.org/10.6084/m9.figshare.1134652},
	abstract = {The CYCLUS Fuel Cycle Simulator is a framework for assessment of nuclear fuel cycle options. While CYCLUS has previously simulated system transitions from the current fuel cycle strategy to a future option, those tran- sitions have never previously been driven by market forces in the simulation. This work includes the first draft of a set of libraries that have been contibuted to the CYCLUS framework to enable a market-driven transition analysis. The CYCLUS simulation framework is incomplete without a suite of dynamically loadable libraries representing the process physics of the nuclear fuel cycle (i.e. mining, fuel fabrication, chemical processing, transmutation, reprocessing, etc.). Within Cycamore, the additional modules repository within the CYCLUS ecosystem, provides some basic li- braries to represent these processes. However, extension of CYCLUS with new capabilities is community-driven, relying on contributions by user-developers. The libraries contributed in this work are examples of such contributions. This work relies heavily on the CycStub repository which included contributions from myself, Kathryn Huff, as well as Matthew Gidden, Anthony Scopatz, Robert Carlsen, Paul Wilson, and Olzhas Rahkimov at the University of Wisconsin - Madison within the Computational Nuclear Engineering Research Group (CNERG).},
	urldate = {2014-08-11},
	journal = {Figshare},
	author = {Huff, Kathryn},
	month = aug,
	year = {2014},
	keywords = {Nuclear, Fuel cycle, Transition, cyclus, Nuclear Fuel Cycle, simulation},
	annote = {http://dx.doi.org/10.6084/m9.figshare.1134652},
	file = {Figshare Download:C\:\\Users\\abachmann\\Zotero\\storage\\9NYZSN8J\\Huff - 2014 - Market Driven Transition Capability for Cyclus Sim.zip:application/x-zip-compressed;Figshare Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\ADMW7EMQ\\1134652.html:text/html;Full Text (HTML):C\:\\Users\\abachmann\\Zotero\\storage\\BJADN7W4\\1134652.html:text/html;github_import4KbTQL:C\:\\Users\\abachmann\\Zotero\\storage\\VKBM3DHT\\Huff - 2014 - Market Driven Transition Capability for Cyclus Sim.zip:application/x-zip-compressed;github_import5xt95E:C\:\\Users\\abachmann\\Zotero\\storage\\FC47PLT6\\Huff - 2014 - Market Driven Transition Capability for Cyclus Sim.zip:application/x-zip-compressed;github_importFQvleC:C\:\\Users\\abachmann\\Zotero\\storage\\3D5HTMMN\\Huff - 2014 - Market Driven Transition Capability for Cyclus Sim.zip:application/x-zip-compressed;github_importOJ7XkH:C\:\\Users\\abachmann\\Zotero\\storage\\R72RUSB2\\Huff - 2014 - Market Driven Transition Capability for Cyclus Sim.zip:application/x-zip-compressed;github_importrGc3Ud:C\:\\Users\\abachmann\\Zotero\\storage\\6T2K78KQ\\Huff - 2014 - Market Driven Transition Capability for Cyclus Sim.zip:application/x-zip-compressed},
}

@article{piet_dynamic_2011,
	title = {Dynamic {Simulations} of {Advanced} {Fuel} {Cycles}},
	volume = {173},
	url = {http://epubs.ans.org/?a=11658},
	number = {3},
	urldate = {2014-08-11},
	journal = {Nuclear Technology},
	author = {Piet, Steven J. and Dixon, Brent W. and Jacobson, Jacob J. and Matthern, Gretchen E. and Shropshire, David E.},
	month = mar,
	year = {2011},
	pages = {227--238},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\6I9MS6EH\\BEPGFXJD.pdf:application/pdf;nt_v173_n3_pp227-238.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\DIUCL988\\nt_v173_n3_pp227-238.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\VZULR8QW\\epubs.ans.org.html:text/html},
}

@techreport{huff_next_2010,
	title = {Next {Generation} {Fuel} {Cycle} {Simulator} {Functions} and {Requirements} {Document}},
	number = {fcrd-sysa-2010-000110},
	institution = {Idaho National Laboratory},
	author = {Huff, Kathryn and Dixon, Brent},
	month = jul,
	year = {2010},
	file = {FCS- Next Generation Fuel Cycle Simulator (FCS) Functions and Requirements.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\J5MYVJX5\\FCS- Next Generation Fuel Cycle Simulator (FCS) Functions and Requirements.pdf:application/pdf;Google Scholar Linked Page:C\:\\Users\\abachmann\\Zotero\\storage\\C8DX6KZN\\JGDIWMHB.pdf:application/pdf;Next Generation Fuel Cycle Simulator (FCS) Functions and Requirements.docx:C\:\\Users\\abachmann\\Zotero\\storage\\DP5HFJFU\\Next Generation Fuel Cycle Simulator (FCS) Functions and Requirements.docx:application/vnd.openxmlformats-officedocument.wordprocessingml.document},
}

@mastersthesis{littell_development_2016,
	address = {Knoxville, TN},
	title = {Development and {Application} of {Nuclear} {Fuel} {Cycle} {Simulators} for {Evaluating} {Potential} {Fuel} {Cycle} {Options}},
	url = {http://trace.tennessee.edu/utk_gradthes/3783/},
	urldate = {2016-08-13},
	school = {University of Tennessee - Knoxville},
	author = {Littell, Jennifer Lynn},
	month = may,
	year = {2016},
	file = {[PDF] tennessee.edu:C\:\\Users\\abachmann\\Zotero\\storage\\5YI8B6LV\\27WVQ9AX.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\85RG92LM\\3783.html:text/html},
}

@article{scopatz_cyclus_2015,
	title = {Cyclus {Archetypes}},
	journal = {Submitted},
	author = {Scopatz, Anthony M. and Huff, Kathryn D. and Gidden, Matthew J. and Carlsen, Robert W. and Flanagan, Robert R. and McGarry, Meghan B. and Opotowsky, Arrielle C. and Schneider, Erich A. and Wilson, Paul P.H.},
	year = {2015},
	file = {paper.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\NPXV2LGU\\2BSTD6DX.pdf:application/pdf},
}

@inproceedings{scopatz_cymetric_2015,
	address = {San Antonio, TX},
	series = {Fuel {Cycle} {Simulators}},
	title = {Cymetric - {A} {Fuel} {Cycle} {Metrics} {Tool} for {Cyclus}},
	volume = {112},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Scopatz, Anthony M. and Opotowsky, Arrielle C. and Wilson, Paul P.H.},
	month = jun,
	year = {2015},
	keywords = {Fuel cycle, Geniusv2, Simulation, C++, Code, Global Evaluation of Nuclear Infrastructure Utilization Scenarios (GENIUS), Technology},
	pages = {81--84},
	file = {032.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\36Q7RFXA\\032.pdf:application/pdf},
}

@techreport{dixon_dynamic_2008,
	address = {Idaho Falls, ID},
	title = {Dynamic {Systems} {Analysis} {Report} for {Nuclear} {Fuel} {Recycle}},
	number = {INL/EXT-08-15201},
	institution = {Idaho National Laboratory},
	author = {Dixon, Brent and Halsey, Bill and Kim, Sonny and Matthern, Gretchen and Piet, Steven and Shropshire, David},
	month = dec,
	year = {2008},
	file = {DSARR R1 reformatted for release final1.doc:C\:\\Users\\abachmann\\Zotero\\storage\\XZ5X3CZG\\DSARR R1 reformatted for release final1.doc:application/msword;FCS- Dynamic Systems Analysis Report for Nuclear Fuel Recycle.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\WAUKST4M\\FCS- Dynamic Systems Analysis Report for Nuclear Fuel Recycle.pdf:application/pdf},
}

@misc{finck_toward_2005,
	title = {Toward a {Sustainable} {Nuclear} {Future}: {Closing} the {Fuel} {Cycle}},
	author = {Finck, Phillip},
	month = oct,
	year = {2005},
	note = {Place: Argonne, IL, United States},
	keywords = {Carbon Dioxide, Fossil Fuels, Sustainability, Nuclear Energy, Climate Change, Closed Fuel Cycle, Energy Demand, Energy Security, Greenhouse Gas Emissions, Growth, Hydrogen Economy},
	file = {CANF-Finck.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\S2LQU2UK\\CANF-Finck.pdf:application/pdf},
}

@techreport{kim_fuel_2010,
	address = {Argonne, IL, United States},
	title = {Fuel {Cycle} {Analysis} of {Once}-{Through} {Nuclear} {Systems}},
	url = {http://www.ipd.anl.gov/anlpubs/2010/09/67863.pdf},
	number = {ANL-FCRD-308},
	institution = {Argonne National Laboratory (ANL)},
	author = {Kim, T. K. and Taiwo, T. A.},
	year = {2010},
	file = {[PDF] from anl.gov:C\:\\Users\\abachmann\\Zotero\\storage\\9N7SJUKL\\Kim and Taiwo - 2010 - Fuel Cycle Analysis of Once-Through Nuclear System.pdf:application/pdf;Fuel_Cycle Analysis_of Once_Through_Nuclear_Systems.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\6A8YNZXI\\UBQ5EPJV.pdf:application/pdf;Google Scholar Linked Page:C\:\\Users\\abachmann\\Zotero\\storage\\YRSPKAYE\\Kim et al. - 2010 - Fuel Cycle Analysis of Once-Through Nuclear System.pdf:application/pdf},
}

@article{passerini_sustainability_2012,
	title = {Sustainability {Features} of {Nuclear} {Fuel} {Cycle} {Options}},
	volume = {4},
	issn = {2071-1050},
	url = {http://www.mdpi.com/2071-1050/4/10/2377/},
	doi = {10.3390/su4102377},
	abstract = {The nuclear fuel cycle is the series of stages that nuclear fuel materials go through in a cradle to grave framework. The Once Through Cycle (OTC) is the current fuel cycle implemented in the United States; in which an appropriate form of the fuel is irradiated through a nuclear reactor only once before it is disposed of as waste. The discharged fuel contains materials that can be suitable for use as fuel. Thus, different types of fuel recycling technologies may be introduced in order to more fully utilize the energy potential of the fuel, or reduce the environmental impacts and proliferation concerns about the discarded fuel materials. Nuclear fuel cycle systems analysis is applied in this paper to attain a better understanding of the strengths and weaknesses of fuel cycle alternatives. Through the use of the nuclear fuel cycle analysis code CAFCA (Code for Advanced Fuel Cycle Analysis), the impact of a number of recycling technologies and the associated fuel cycle options is explored in the context of the U.S. energy scenario over 100 years. Particular focus is given to the quantification of Uranium utilization, the amount of Transuranic Material (TRU) generated and the economics of the different options compared to the base-line case, the OTC option. It is concluded that LWRs and the OTC are likely to dominate the nuclear energy supply system for the period considered due to limitations on availability of TRU to initiate recycling technologies. While the introduction of U-235 initiated fast reactors can accelerate their penetration of the nuclear energy system, their higher capital cost may lead to continued preference for the LWR-OTC cycle.},
	language = {en},
	number = {12},
	urldate = {2013-04-02},
	journal = {Sustainability},
	author = {Passerini, Stefano and Kazimi, Mujid},
	month = sep,
	year = {2012},
	keywords = {Nuclear Fuel Cycle, analysis, nuclear reactor technologies},
	pages = {2377--2398},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\HT9P4N5N\\Passerini and Kazimi - 2012 - Sustainability Features of Nuclear Fuel Cycle Opti.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\PNKGRYZV\\2377.html:text/html;sustainability-04-02377.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\WDBSVM7N\\sustainability-04-02377.pdf:application/pdf},
}

@article{macal_everything_2016,
	title = {Everything you need to know about agent-based modelling and simulation},
	volume = {10},
	issn = {1747-7778},
	url = {http://www.palgrave-journals.com/jos/journal/v10/n2/full/jos20167a.html},
	doi = {10.1057/jos.2016.7},
	abstract = {This paper addresses the background and current state of the field of agent-based modelling and simulation (ABMS). It revisits the issue of ABMS represents as a new development, considering the extremes of being an overhyped fad, doomed to disappear, or a revolutionary development, shifting fundamental paradigms of how research is conducted. This paper identifies key ABMS resources, publications, and communities. It also proposes several complementary definitions for ABMS, based on practice, intended to establish a common vocabulary for understanding ABMS, which seems to be lacking. It concludes by suggesting research challenges for ABMS to advance and realize its potential in the coming years.},
	language = {en},
	number = {2},
	urldate = {2016-05-14},
	journal = {Journal of Simulation},
	author = {Macal, C. M.},
	month = may,
	year = {2016},
	keywords = {agent-based modeling and simulation, computational social simulation, modeling human behavior, multi-agent system},
	pages = {144--156},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\C63NR6C3\\Macal - 2016 - Everything you need to know about agent-based mode.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\X9I3GXTT\\jos20167a.html:text/html},
}

@book{tsoulfanidis_nuclear_2013,
	address = {La Grange Park, Illinois, USA},
	title = {The {Nuclear} {Fuel} {Cycle}},
	isbn = {978-0-89448-460-5},
	abstract = {"The Nuclear Fuel Cycle" has been extensively revised since its previous edition published in 1999 and it includes a whole new chapter on nuclear safeguards. The book covers all aspects of the nuclear fuel cycle-from cradle to grave. Topics include the available nuclear fuel resources (uranium and thorium), extraction of the metals from the ore, fabrication of nuclear fuel, use of the fuel for power generation, and management and disposal of used fuel and radioactive wastes. Other topics discussed are basic reactor physics, in-core and out-of-core fuel management, possible fuel cycles, nuclear power economics, and nuclear safeguards. The various methods of generating electricity are also described and compared, concentrating on their environmental effects.},
	publisher = {American Nuclear Society},
	author = {Tsoulfanidis, Nicholas},
	year = {2013},
	annote = {00177},
}

@article{baschwitz_when_2017,
	title = {When would fast reactors become competitive with light water reactors? {Methodology} and key parameters},
	volume = {100},
	issn = {0149-1970},
	shorttitle = {When would fast reactors become competitive with light water reactors?},
	url = {http://www.sciencedirect.com/science/article/pii/S0149197017301336},
	doi = {10.1016/j.pnucene.2017.05.028},
	abstract = {Although economics will certainly not be the only criterion for deploying fast reactors, it will be an important one. In this paper we will present a method for analysing their competitiveness in comparison with thermal neutron reactors. We will use the levelised cost of electricity (LCOE) method to compare the production costs of each technology. For forecasting the uranium cost, which is an important question for competitiveness, we have proposed a model based on supply curve. This model approximates the uranium costs over the assumed 60-year operating lifetime of new reactors, according to their commissioning date. Concerning the fuel cycle costs, we have taken into account the fact that they will differ according to whether or not the reactor is in a country which has already chosen to treat and recycle spent fuel (back-end of the cycle). A uranium equivalent value is then calculated for which the kWh costs of each reactor technology would be the same. This enables us to determine the period when FRs will become competitive according to various parameters. The uranium supply curve appears to be the most influential parameter for any given nuclear demand, followed by the discount rate, prior choices regarding the back-end of the cycle, and the additional investment cost of FRs in comparison with PWRs.},
	journal = {Progress in Nuclear Energy},
	author = {Baschwitz, Anne and Mathonnière, Gilles and Gabriel, Sophie and Devezeaux de Lavergne, Jean-Guy and Pincé, Yann},
	month = sep,
	year = {2017},
	keywords = {Recycling, Breakeven cost, FR competitiveness, Levelised cost of electricity, Uranium supply curve},
	pages = {103--113},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\AGX3CGVC\\Baschwitz et al. - 2017 - When would fast reactors become competitive with l.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\IL45N8AI\\S0149197017301336.html:text/html},
}

@techreport{skutnik_origen-based_2017,
	title = {{ORIGEN}-based {Nuclear} {Fuel} {Inventory} {Module} for {Fuel} {Cycle} {Assessment}: {Final} {Project} {Report}},
	shorttitle = {{ORIGEN}-based {Nuclear} {Fuel} {Inventory} {Module} for {Fuel} {Cycle} {Assessment}},
	url = {https://www.osti.gov/scitech/biblio/1364128},
	institution = {Univ. of Tennessee, Knoxville, TN (United States)},
	author = {Skutnik, Steven E.},
	year = {2017},
	annote = {https://www.osti.gov/scitech/servlets/purl/1364128},
}

@article{yacout_visionverifiable_2006,
	title = {{VISION}–{Verifiable} {Fuel} {Cycle} {Simulation} of {Nuclear} {Fuel} {Cycle} {Dynamics}},
	journal = {Waste Management},
	author = {Yacout, AM and Jacobson, JJ and Matthern, GE and Piet, SJ and Shropshire, DE and Laws, CT},
	year = {2006},
	file = {3394908.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\3V77IV87\\9T3W4J57.pdf:application/pdf},
}

@inproceedings{djokic_application_2015,
	address = {Paris, France},
	series = {{LLNL}-{CONF}-669315},
	title = {The {Application} of {CYCLUS} to {Fuel} {Cycle} {Transition} {Analysis}},
	url = {https://www.osti.gov/biblio/1241931-application-cyclus-fuel-cycle-transition-analysis},
	booktitle = {Proceedings of {Global} 2015},
	author = {Djokic, Denia and Scopatz, Anthony M. and Greenberg, Harris R. and Huff, Kathryn D. and Nibbelink, Russell P. and Fratoni, Massimiliano},
	month = sep,
	year = {2015},
	file = {5061- final.docx:C\:\\Users\\abachmann\\Zotero\\storage\\BLSELSUA\\5061- final.docx:application/vnd.openxmlformats-officedocument.wordprocessingml.document;5061- final.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\3GZV2RZM\\U9VFZXBD.pdf:application/pdf},
}

@phdthesis{gidden_agent-based_2015,
	address = {Madison, WI, United States},
	type = {{PhD} {Thesis}},
	title = {An {Agent}-{Based} {Modeling} {Framework} and {Application} for the {Generic} {Nuclear} {Fuel} {Cycle}},
	abstract = {Key components of a novel methodology and implementation of an agent-based, dynamic nuclear fuel cycle simulator, Cyclus , are presented. The nuclear fuel cycle is a complex, physics-dependent supply chain. To date, existing dynamic simulators have not treated constrained fuel supply, time-dependent, isotopic-quality based demand, or fuel fungibility particularly well. Utilizing an agent-based methodology that incorporates sophisticated graph theory and operations research techniques can overcome these deficiencies. This work describes a simulation kernel and agents that interact with it, highlighting the Dynamic Resource Exchange (DRE), the supply-demand framework at the heart of the kernel. The key agent-DRE interaction mechanisms are described, which enable complex entity interaction through the use of physics and socio-economic models. The translation of an exchange instance to a variant of the Multicommodity Transportation Problem, which can be solved feasibly or optimally, follows. An extensive investigation of solution performance and fidelity is then presented. Finally, recommendations for future users of Cyclus and the DRE are provided.},
	school = {University of Wisconsin},
	author = {Gidden, Matthew J.},
	month = mar,
	year = {2015},
	file = {gidden_agent-based_2015.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\TLJXGN7U\\gidden_agent-based_2015.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\ZTWMYGIL\\1.html:text/html},
}

@techreport{guerin_benchmark_2009,
	type = {Technical {Report}},
	title = {A {Benchmark} {Study} of {Computer} {Codes} for {System} {Analysis} of the {Nuclear} {Fuel} {Cycle}},
	url = {http://dspace.mit.edu/handle/1721.1/75245},
	urldate = {2014-08-19},
	institution = {Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program},
	author = {Guerin, Laurent and Feng, Bo and Hejzlar, Pavel and Forget, Benoit and Kazimi, Mujid S. and Van Den Durpel, Luc and Yacout, Abdellatif and Taiwo, Temi and Dixon, Brent W. and Matthern, Grechen and Boucher, Lionel and Delpech, Marc and Girieud, Richard and Meyer, Maryan},
	month = apr,
	year = {2009},
	keywords = {Technical Report},
	annote = {Electric Power Research Institute},
	file = {nsc-wpfc-doc2012-16.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\6L95TQLY\\nsc-wpfc-doc2012-16.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\9GWFAYS2\\75245.html:text/html;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\MZSGQXA8\\75245.html:text/html},
}

@misc{harlan_x-energy_2018,
	title = {X-energy {Xe}-100 {Reactor} initial {NRC} meeting},
	url = {https://www.nrc.gov/docs/ML1825/ML18253A109.pdf},
	language = {English},
	urldate = {2019-09-20},
	author = {Harlan, Bowers},
	month = sep,
	year = {2018},
	note = {Place: Rockville, MD},
	file = {X-energy Xe-100 Reactor initial NRC meeting:C\:\\Users\\abachmann\\Zotero\\storage\\FCHPILF9\\X-energy Xe-100 Reactor initial NRC meeting.pdf:application/pdf},
}

@misc{noauthor_reactor_nodate,
	title = {Reactor: {Xe}-100},
	shorttitle = {Reactor},
	url = {https://x-energy.com/reactors/xe-100},
	abstract = {We’re focused on Gen-IV High-Temperature Gas-cooled Reactors (HTGR) as the technology of choice, with advantages in sustainability, economics, reliability and safety.},
	language = {en-US},
	urldate = {2022-07-21},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\AYS9QBKZ\\xe-100.html:text/html},
}

@techreport{us_energy_information_administration_electric_2022,
	title = {Electric {Power} {Monthly}},
	url = {https://www.eia.gov/electricity/monthly/},
	urldate = {2022-07-21},
	author = {{U.S. Energy Information Administration}},
	month = may,
	year = {2022},
	annote = {Table 6.7.B Capacity Factors for Utility Scale Generators Not Primarily Using Fossil Fuels},
	file = {Electric Power Monthly - U.S. Energy Information Administration (EIA):C\:\\Users\\abachmann\\Zotero\\storage\\7AZXIWJB\\monthly.html:text/html},
}

@misc{nuscale_technology_nodate,
	title = {Technology {Overview} {\textbackslash}textbar {NuScale} {Power}},
	url = {https://www.nuscalepower.com/technology/technology-overview},
	urldate = {2022-07-21},
	author = {{NuScale}},
	note = {Publication Title: NuScale},
	file = {Technology Overview | NuScale Power:C\:\\Users\\abachmann\\Zotero\\storage\\E36UBM52\\technology-overview.html:text/html},
}

@misc{nuscale_nuscale_2022,
	title = {{NuScale} {Small} {Modular} {Reactor}},
	url = {https://s24.q4cdn.com/104943030/files/doc_downloads/factsheet/nuscale-smr-fact-sheet.pdf},
	urldate = {2022-06-29},
	publisher = {NuScale},
	author = {{NuScale}},
	year = {2022},
	file = {nuscale-smr-fact-sheet.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\F9GSK8BH\\nuscale-smr-fact-sheet.pdf:application/pdf},
}

@techreport{noauthor_total_2022,
	type = {Technical {Report}},
	title = {Total {Energy} {Monthly} {Data}},
	url = {https://www.eia.gov/totalenergy/data/monthly/},
	urldate = {2022-07-20},
	institution = {U.S. Energy Information Administration},
	month = jun,
	year = {2022},
	file = {Total Energy Monthly Data - U.S. Energy Information Administration (EIA):C\:\\Users\\abachmann\\Zotero\\storage\\J9G87VDM\\monthly.html:text/html},
}

@techreport{noauthor_global_2022,
	title = {Global {Electricity} {Review} 2022},
	url = {https://ember-climate.org/insights/research/global-electricity-review-2022/},
	abstract = {Wind and solar, the fastest growing sources of electricity, reach a record ten percent of global electricity in 2021; all clean power is now 38\% of supply.},
	language = {en-US},
	urldate = {2022-07-20},
	institution = {Ember},
	month = mar,
	year = {2022},
	file = {2022 - Global Electricity Review 2022.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\HMD9V2AQ\\2022 - Global Electricity Review 2022.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\SQA2BBVR\\global-electricity-review-2022.html:text/html},
}

@misc{x-energy_triso-x_2022,
	title = {{TRISO}-{X} {Submits} {First} {Ever} {High}-{Assay} {Low}-{Enriched} {Uranium} {Fuel} {Fabrication} {Facility} {License} {Application} to the {Nuclear} {Regulatory} {Commission}},
	url = {https://x-energy.com/media/news-releases/triso-x-submits-first-ever-high-assay-low-enriched-uranium-fuel-fabrication-facility-license-application-to-the-nuclear-regulatory-commission},
	abstract = {The TRISO-X Fuel Fabrication Facility (TF3) will be the nation’s first 10 CFR 70 Category II fuel facility dedicated exclusively to fueling HALEU based reactors},
	language = {en-US},
	urldate = {2022-07-01},
	author = {{X-energy}},
	month = apr,
	year = {2022},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\T24BCW7B\\triso-x-submits-first-ever-high-assay-low-enriched-uranium-fuel-fabrication-facility-license-ap.html:text/html},
}

@techreport{whitaker_uranium_2019,
	title = {Uranium {Enrichment} {Plant} {Characteristics} - {A} {Training} {Manual} for the {IAEA}},
	url = {https://www.osti.gov/servlets/purl/1606938/},
	language = {en},
	number = {ORNL/TM–2019/1311, 1606938},
	urldate = {2022-07-01},
	institution = {Oak Ridge National Lab},
	author = {Whitaker, J. and McGirl, Natalie and Tucker, Diana and Kapsimalis, Ann},
	month = oct,
	year = {2019},
	doi = {10.2172/1606938},
	pages = {ORNL/TM--2019/1311, 1606938},
}

@misc{noauthor_enrichment_nodate,
	title = {Enrichment {Cascades}},
	url = {https://fas.org/issues/nonproliferation-counterproliferation/nuclear-fuel-cycle/uranium-enrichment-gas-centrifuge-technology/enrichment-cascades/},
	abstract = {No single existing centrifuge can enrich uranium from its natural concentration of about 0.7 percent uranium-235 to the 3 to 5 percent required to fuel a nuclear reactor. In addition, the throughput of a centrifuge is very small compared to the consumption of a reactor. To multiply the effects of t},
	language = {en-US},
	urldate = {2022-07-01},
	note = {Publication Title: Federation Of American Scientists},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\KS43XUT8\\enrichment-cascades.html:text/html},
}

@article{glaser_characteristics_2008,
	title = {Characteristics of the {Gas} {Centrifuge} for {Uranium} {Enrichment} and {Their} {Relevance} for {Nuclear} {Weapon} {Proliferation}},
	volume = {16},
	issn = {0892-9882},
	url = {https://doi.org/10.1080/08929880802335998},
	doi = {10.1080/08929880802335998},
	abstract = {This article presents an analytical model, originally developed in the 1980s, for the gas centrifuge and uses this methodology to determine the main design and operational characteristics of several hypothetical centrifuge designs. A series of simulations for a typical first-generation machine is used to assess the relevance of important breakout scenarios, including batch recycling and cascade interconnection, using either natural uranium or preenriched material as feedstock.},
	number = {1-2},
	urldate = {2022-07-01},
	journal = {Science \& Global Security},
	author = {GLASER, ALEXANDER},
	month = oct,
	year = {2008},
	pages = {1--25},
	annote = {Publisher: Routledge \_eprint: https://doi.org/10.1080/08929880802335998},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\WVYXSHPJ\\I7RPY4FW.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\XY3X743D\\08929880802335998.html:text/html},
}

@book{krass_uranium_2020,
	title = {Uranium {Enrichment} and {Nuclear} {Weapon} {Proliferation}},
	isbn = {978-1-00-020054-6},
	abstract = {Originally published in 1983, this book presents both the technical and political information necessary to evaluate the emerging threat to world security posed by recent advances in uranium enrichment technology. Uranium enrichment has played a relatively quiet but important role in the history of efforts by a number of nations to acquire nuclear weapons and by a number of others to prevent the proliferation of nuclear weapons. For many years the uranium enrichment industry was dominated by a single method, gaseous diffusion, which was technically complex, extremely capital-intensive, and highly inefficient in its use of energy. As long as this remained true, only the richest and most technically advanced nations could afford to pursue the enrichment route to weapon acquisition. But during the 1970s this situation changed dramatically. Several new and far more accessible enrichment techniques were developed, stimulated largely by the anticipation of a rapidly growing demand for enrichment services by the world-wide nuclear power industry. This proliferation of new techniques, coupled with the subsequent contraction of the commercial market for enriched uranium, has created a situation in which uranium enrichment technology might well become the most important contributor to further nuclear weapon proliferation. Some of the issues addressed in this book are: A technical analysis of the most important enrichment techniques in a form that is relevant to analysis of proliferation risks; A detailed projection of the world demand for uranium enrichment services; A summary and critique of present institutional non-proliferation arrangements in the world enrichment industry, and An identification of the states most likely to pursue the enrichment route to acquisition of nuclear weapons.},
	language = {en},
	publisher = {Routledge},
	author = {Krass, Allan S. and Boskma, Peter and Elzen, Boelie and Smit, Wim A. and Institute, Stockholm International Peace Research},
	month = nov,
	year = {2020},
	keywords = {Political Science / General},
	annote = {Google-Books-ID: emMPEAAAQBAJ},
}

@book{noauthor_status_2021,
	address = {Vienna},
	series = {{TECDOC} {Series}},
	title = {Status and {Trends} in {Pyroprocessing} of {Spent} {Nuclear} {Fuels}},
	isbn = {978-92-0-122921-2},
	url = {https://www.iaea.org/publications/11062/status-and-trends-in-pyroprocessing-of-spent-nuclear-fuels},
	number = {1967},
	publisher = {INTERNATIONAL ATOMIC ENERGY AGENCY},
	year = {2021},
	file = {Status and Trends in Pyroprocessing of Spent Nucle.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\JD9H7RZ6\\Status and Trends in Pyroprocessing of Spent Nucle.pdf:application/pdf;Status and Trends in Pyroprocessing of Spent Nuclear Fuels | IAEA:C\:\\Users\\abachmann\\Zotero\\storage\\BY3CI7LT\\status-and-trends-in-pyroprocessing-of-spent-nuclear-fuels.html:text/html},
}

@misc{mulder_overview_2021,
	title = {Overview of {X}-{Energy}'s 200 {MWth} {Xe}-100 {Reactor}},
	url = {https://www.nationalacademies.org/documents/embed/link/LF2255DA3DD1C41C0A42D3BEF0989ACAECE3053A6A9B/file/DCB77DCC95AEF75D0CA6FE9C717CAA34436F7817D15A},
	author = {Mulder, Eben J.},
	month = jan,
	year = {2021},
	file = {_.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\YESYHNFE\\_.pdf:application/pdf},
}

@misc{reyes_nuscale_2021,
	title = {{NuScale} {Power} - {A} {Scalable} {Clean} {Energy} {Solution}},
	urldate = {2022-06-29},
	author = {Reyes, Jose},
	month = jan,
	year = {2021},
	file = {_.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\YVJU7NL7\\_.pdf:application/pdf},
}

@misc{reyes_nuscale_2021-1,
	title = {{NuScale} {Response} to {NASEM} {Questionnaire}},
	url = {https://www.nationalacademies.org/event/07-14-2020/docs/DDB3F347BF200800E9B24B83380F2347BC20918B48C0},
	urldate = {2022-06-29},
	author = {Reyes, Jose},
	month = jul,
	year = {2021},
	file = {_.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\LQNWE94E\\_.pdf:application/pdf},
}

@misc{noauthor_usnc_2021,
	title = {{USNC} {Micro} {Modular} {Reacotr} ({MMR} {Block} 1) {Technical} {Information}},
	url = {https://usnc.com/assets/media-kit/[022989][01]%20MMR%20Technical%20Information%20Document.pdf?v=30823a846f},
	urldate = {2022-06-29},
	year = {2021},
	file = {[022989][01] MMR Technical Information Document.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\47F2LEL4\\[022989][01] MMR Technical Information Document.pdf:application/pdf},
}

@misc{reyes_correction_2022,
	title = {Correction of {Factual} {Error} in {PNAS} {Paper} titled “{Nuclear} waste from small modular reactors”},
	url = {https://newsroom.nuscalepower.com/news/},
	language = {en-US},
	urldate = {2022-06-29},
	author = {Reyes, Jose N.},
	month = may,
	year = {2022},
	file = {News  NuScale Power.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\DH9MRRYI\\News  NuScale Power.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\S3HIUHU2\\news.html:text/html},
}

@misc{noauthor_10_2006,
	title = {10 {CFR} 50.68 {Criticality} accident requirements.},
	url = {https://www.nrc.gov/reading-rm/doc-collections/cfr/part050/part050-0068.html},
	urldate = {2022-06-28},
	month = nov,
	year = {2006},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\NG6DRTX2\\part050-0068.html:text/html},
}

@inproceedings{mascolino_impact_2022,
	address = {Anaheim, CA, United States},
	title = {Impact of {LEU} {U}-{10Mo} {Fuel} {Impurities} on the {Massachusetts} {Institute} of {Technology} {Reactor}'s {Neutronics} {Performance}},
	volume = {126},
	language = {eng},
	booktitle = {Transactions of the {American} {Nuclear} {Soceity} {Annual} {Meeting}},
	author = {Mascolino, Valerio and Jamison, Laura M. and Cowherd, Wilson and Anderson, Kyle E. and Stillman, John A. and Hu, Lin-Wen and Wilson, Erik H.},
	month = jun,
	year = {2022},
	file = {Impact of LEU U-10Mo Fuel Impurities on the Massac.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\TZW43Z84\\X54EBHDS.pdf:application/pdf},
}

@misc{us_energy_information_administration_annual_2022,
	title = {Annual {Energy} {Outlook} 2022 - {U}.{S}. {Energy} {Information} {Administration} ({EIA})},
	url = {https://www.eia.gov/outlooks/aeo/narrative/electricity/sub-topic-01.php},
	abstract = {Energy Information Administration - EIA - Official Energy Statistics from the U.S. Government},
	urldate = {2022-06-10},
	author = {{U.S. Energy Information Administration}},
	month = mar,
	year = {2022},
	note = {Publication Title: U.S. Energy Information Administration},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\SMV5P3GE\\sub-topic-01.html:text/html},
}

@misc{world_nuclear_news_nuscale_2021,
	title = {{NuScale} {SMR} plants become {VOYGR} : {New} {Nuclear} - {World} {Nuclear} {News}},
	url = {https://www.world-nuclear-news.org/Articles/NuScale-SMR-plants-become-VOYGR},
	urldate = {2022-06-10},
	author = {{World Nuclear News}},
	month = dec,
	year = {2021},
	note = {Publication Title: World Nuclear News},
	file = {NuScale SMR plants become VOYGR \: New Nuclear - World Nuclear News:C\:\\Users\\abachmann\\Zotero\\storage\\6NXKEPEX\\NuScale-SMR-plants-become-VOYGR.html:text/html},
}

@misc{noauthor_licensing_nodate,
	title = {Licensing {\textbackslash}textbar {NuScale} {Power}},
	url = {https://www.nuscalepower.com/technology/licensing},
	urldate = {2022-06-10},
	file = {Licensing | NuScale Power:C\:\\Users\\abachmann\\Zotero\\storage\\HQDHSJBS\\licensing.html:text/html},
}

@misc{nichol_current_2021,
	title = {Current {Status} of {Advanced} {Nuclear} {Reactors}},
	url = {https://files.nc.gov/ncdeq/energy-policy-council/August_18_2021_EPC_Meeting.pdf},
	language = {en},
	urldate = {2022-06-10},
	author = {Nichol, Marc},
	month = aug,
	year = {2021},
	file = {Nichol - Current Status of Advanced Nuclear Reactors.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\YH4J29C5\\Nichol - Current Status of Advanced Nuclear Reactors.pdf:application/pdf},
}

@misc{noauthor_nuclear_1983,
	title = {Nuclear {Waste} {Policy} {Act} of 1982},
	copyright = {Text is government work},
	shorttitle = {Text - {H}.{R}.3809 - 97th {Congress} (1981-1982)},
	url = {http://www.congress.gov/},
	abstract = {Text for H.R.3809 - 97th Congress (1981-1982): Nuclear Waste Policy Act of 1982},
	language = {eng},
	urldate = {2022-06-08},
	month = jan,
	year = {1983},
	annote = {Archive Location: 1981/1982},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\JW2AM8XU\\text.html:text/html;Udall - 1983 - Text - H.R.3809 - 97th Congress (1981-1982) Nucle.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\3CUR3N9B\\Udall - 1983 - Text - H.R.3809 - 97th Congress (1981-1982) Nucle.pdf:application/pdf},
}

@article{stahala_investigation_2008,
	title = {Investigation of {Yucca} {Mountain} repository capacity for the {US} spent nuclear fuel inventory},
	volume = {35},
	issn = {0306-4549},
	url = {https://www.sciencedirect.com/science/article/pii/S0306454907002927},
	doi = {10.1016/j.anucene.2007.11.002},
	abstract = {An analytical decay heat model was developed to evaluate the US inventory of commercial spent nuclear fuel (SNF). The model was benchmarked against the results from ORIGEN-ARP 5.01. The new analytical SNF decay heat model was applied to actual (thru 2002) and projected SNF data. The total decay heat from the 63,000 MT commercial SNF at year 2012 was estimated at 182MW. According to the thermal loading analysis using a mountain-scale heat transfer model, a 4.9km2 (1165acre) site designated for SNF disposal was found to have the capacity to store more SNF than the statutory limit of 70,000 MTIHM. The maximum capacity available for SNF disposal at the Yucca Mountain site is dependent upon the thermal loading strategy chosen and SNF cooling time before emplacement. It was also shown that using high burnup SNF and adjusting the drift spacing, the capacity of the repository could be maximized on a per energy production basis, although some additional cooling may be necessary. Future work needs to consider extending the ‘footprint’ of the repository, applying non-uniform SNF loading into the drifts, and the impact of spent fuel reprocessing and other decay heat management strategies.},
	language = {en},
	number = {6},
	urldate = {2022-06-07},
	journal = {Annals of Nuclear Energy},
	author = {Stahala, Mike P. and Yim, Man-Sung and McNelis, David N.},
	month = jun,
	year = {2008},
	pages = {1056--1067},
	file = {ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\VZSB79MM\\S0306454907002927.html:text/html;Stahala et al. - 2008 - Investigation of Yucca Mountain repository capacit.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\3BMLZYVG\\Stahala et al. - 2008 - Investigation of Yucca Mountain repository capacit.pdf:application/pdf},
}

@misc{noauthor_yucca_nodate,
	title = {Yucca {Mountain} {Report}},
	url = {http://mydocs.epri.com/docs/CorporateDocuments/SectorPages/Portfolio/Nuclear/YuccaMtn.html},
	urldate = {2022-06-07},
	file = {Yucca Mountain Report:C\:\\Users\\abachmann\\Zotero\\storage\\M5YJP7JB\\YuccaMtn.html:text/html},
}

@article{gottaut_results_1990,
	title = {Results of experiments at the {AVR} reactor},
	volume = {121},
	issn = {00295493},
	url = {https://linkinghub.elsevier.com/retrieve/pii/002954939090099J},
	doi = {10.1016/0029-5493(90)90099-J},
	language = {en},
	number = {2},
	urldate = {2022-05-26},
	journal = {Nuclear Engineering and Design},
	author = {Gottaut, H. and Krüger, K.},
	month = jul,
	year = {1990},
	pages = {143--153},
	file = {Gottaut and Krüger - 1990 - Results of experiments at the AVR reactor.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\6Q4D4MM6\\Gottaut and Krüger - 1990 - Results of experiments at the AVR reactor.pdf:application/pdf},
}

@misc{us_department_of_energy_office_of_nuclear_energy_advanced_nodate,
	title = {Advanced {Reactor} {Demonstration} {Program}},
	url = {https://www.energy.gov/ne/advanced-reactor-demonstration-program},
	abstract = {The Advanced Reactor Demonstration Program (ARDP) will help private industry demonstrate advanced nuclear reactors in the United States},
	language = {en},
	urldate = {2022-05-20},
	author = {{U.S. Department of Energy Office of Nuclear Energy}},
	note = {Publication Title: Energy.gov},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\LG3ECXZA\\advanced-reactor-demonstration-program.html:text/html},
}

@misc{world_nuclear_association_plans_2022,
	title = {Plans for {New} {Nuclear} {Reactors} {Worldwide} - {World} {Nuclear} {Association}},
	url = {https://world-nuclear.org/information-library/current-and-future-generation/plans-for-new-reactors-worldwide.aspx},
	urldate = {2022-05-20},
	author = {{World Nuclear Association}},
	month = may,
	year = {2022},
	note = {Publication Title: World Nuclear Association},
	file = {Plans for New Nuclear Reactors Worldwide - World Nuclear Association:C\:\\Users\\abachmann\\Zotero\\storage\\3E79PS2N\\plans-for-new-reactors-worldwide.html:text/html},
}

@misc{us_energy_information_administration_electricity_2022,
	title = {Electricity in the {U}.{S}. - {U}.{S}. {Energy} {Information} {Administration} ({EIA})},
	url = {https://www.eia.gov/energyexplained/electricity/electricity-in-the-us.php},
	urldate = {2022-05-20},
	author = {{U.S Energy Information Administration}},
	month = apr,
	year = {2022},
	file = {Electricity in the U.S. - U.S. Energy Information Administration (EIA):C\:\\Users\\abachmann\\Zotero\\storage\\JI4SDXSI\\electricity-in-the-us.html:text/html},
}

@techreport{us_energy_information_administration_2020_2021,
	title = {2020 {Domestic} {Uranium} {Production} {Report}},
	url = {https://www.eia.gov//uranium/production/annual/index.php},
	abstract = {Energy Information Administration - EIA - Official Energy Statistics from the U.S. Government},
	urldate = {2022-04-29},
	institution = {U.S. Energy Information Administration},
	author = {{U.S. Energy Information Administration}},
	month = may,
	year = {2021},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\QUQQQ6FT\\annual.html:text/html;Vest - 2020 - 2020 Domestic Uranium Production Report.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\G9GK4EUQ\\Vest - 2020 - 2020 Domestic Uranium Production Report.pdf:application/pdf},
}

@misc{richter_isotopic_2022,
	title = {Isotopic {Fuel} {Compositions} in the {Sangamon200} {Model}},
	url = {https://zenodo.org/record/6426312},
	abstract = {The seven csv files each correspond to a different level of fuel burnup in the Sangamon200 (a 200 MWth pebble-bed HTGR) fuel pebbles. fresh\_comp.csv provides the composition for UCO in fresh pebbles. 1pass\_comp.csv provides the fuel composition in pebbles that have gone through one six month pass, 2pass\_comp.csv have been through two six month passes, and so forth.},
	urldate = {2022-04-11},
	publisher = {Zenodo},
	author = {Richter, Zoe},
	month = apr,
	year = {2022},
	doi = {10.5281/zenodo.6426312},
	annote = {Type: dataset},
	file = {Zenodo Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\LT89L8JK\\6426312.html:text/html},
}

@misc{noauthor_spent_nodate,
	title = {Spent {Fuel} {Storage} {\textbackslash}textbar {NuScale} {Power}},
	url = {https://www.nuscalepower.com/benefits/safety-features/spent-fuel-storage},
	urldate = {2022-04-07},
	file = {Spent Fuel Storage | NuScale Power:C\:\\Users\\abachmann\\Zotero\\storage\\23T4GYRK\\spent-fuel-storage.html:text/html},
}

@misc{noauthor_x-energy_2021,
	title = {X-energy is {Developing} a {Pebble} {Bed} {Reactor} {That} {They} {Say} {Can}'t {Melt} {Down}},
	url = {https://www.energy.gov/ne/articles/x-energy-developing-pebble-bed-reactor-they-say-cant-melt-down},
	abstract = {This pebble bed, high-temperature gas-cooled reactor can't melt down, according to X-energy.},
	language = {en},
	urldate = {2022-04-07},
	month = jan,
	year = {2021},
	note = {Publication Title: Energy.gov},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\S4XFP2L3\\x-energy-developing-pebble-bed-reactor-they-say-cant-melt-down.html:text/html},
}

@techreport{hyland_effects_2015,
	address = {Nuclear Energy Agency of the OECD (NEA)},
	title = {The {Effects} of the {Uncertainty} of {Input} {Parameters} on {Nuclear} {Fuel} {Cycle} {Scenario} {Studies}},
	abstract = {Full text of publication follows: Decisions taken in the near term can have large consequences on the eventual outcomes of a chosen fuel cycle due to the long-time frames involved in the development, construction, operation and decommissioning of nuclear facilities, and the storage of nuclear waste Numerous elements of future fuel cycles, such as the future nuclear energy demand and costs associated with future fuel cycle facilities that are not available commercially today, are not currently known, or not well-known Due to these uncertainties, many countries are currently evaluating potential future nuclear energy scenarios, employing fuel cycle scenario studies as a mechanism to inform decisions on future reactor types, fuel types, and other fuel cycle facilities Fuel cycle scenario studies are complex, involving many interconnecting components Many of the input parameters have large uncertainties However, not all uncertainties will have a significant impact on each of the evaluation metrics of the fuel cycle Certain evaluation metrics will be more sensitive to different input parameters The Nuclear Energy Agency's Expert Group on Advanced Fuel Cycle Scenarios has undertaken a study to evaluate the effects of the uncertainties of input parameters on the outcomes of fuel cycle scenario studies The goal of this work is to provide guidance on which input parameters it is important to investigate thoroughly and know well, and which components can be less well-known, given the objectives of a particular study Each participating member chose their own scenario code, the choices of which include: VISION, COSI, FAMILY, COSAC and EVOLCODE A simplified nuclear fuel cycle scenario was employed as a reference case to first ensure that all codes performed comparable analyses of the scenario, to identify any differences attributable to the modeling approaches between the codes, and to provide a baseline against which to evaluate sensitivities The reference scenario involves the transition from a fleet of UOX fueled PWRs to a fleet of MOX fueled FRs under a constant nuclear energy demand The sensitivities of output metrics such as resource consumption, enrichment requirements, plutonium and spent fuel inventories, and reprocessing capacity to the varied parameters were evaluated Varied input parameters include: nuclear energy demand and energy demand profile, spent nuclear fuel cooling time, fresh fuel fabrication time, date and rate of introduction of the fast reactors, fuel burnup, fuel composition (including the minor actinide content of the fast reactor fuel in case of MA transmutation), fast reactor breeding ratio, reactor lifetime, and introduction date, capacity, and losses of the reprocessing plant The results show how the output metrics are affected by the choice of scenario code, with an explanation of which assumptions underlie these effects The results also show the relative impact of each parameter on each output metric If the feasibility of the scenario in terms of fissile materials availability is threatened, possible adjustments of input parameters are explored (authors)},
	author = {Hyland, B. and Wojtaszek, D. and Coquelet-Pascal, C. and Freynet, D. and Alvarez-Velarde, F. and Garciac, M. and Dixon, B. and Gabrielli, F. and Vezzoni, B. and Glinatsis, G. and Ono, K. and Ohtaki, A. and Malambu, E. and Carlier, B. and Cornet, S.},
	year = {2015},
	pages = {45},
	annote = {NEA-NSC-R–2015-2 INIS Reference Number: 47093714},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\43VEJ923\\Hyland et al. - 2015 - The Effects of the Uncertainty of Input Parameters.pdf:application/pdf},
}

@article{saltelli_variance_2010,
	title = {Variance based sensitivity analysis of model output. {Design} and estimator for the total sensitivity index},
	volume = {181},
	issn = {0010-4655},
	url = {https://www.sciencedirect.com/science/article/pii/S0010465509003087},
	doi = {10.1016/j.cpc.2009.09.018},
	abstract = {Variance based methods have assessed themselves as versatile and effective among the various available techniques for sensitivity analysis of model output. Practitioners can in principle describe the sensitivity pattern of a model Y=f(X1,X2,…,Xk) with k uncertain input factors via a full decomposition of the variance V of Y into terms depending on the factors and their interactions. More often practitioners are satisfied with computing just k first order effects and k total effects, the latter describing synthetically interactions among input factors. In sensitivity analysis a key concern is the computational cost of the analysis, defined in terms of number of evaluations of f(X1,X2,…,Xk) needed to complete the analysis, as f(X1,X2,…,Xk) is often in the form of a numerical model which may take long processing time. While the computational cost is relatively cheap and weakly dependent on k for estimating first order effects, it remains expensive and strictly k-dependent for total effect indices. In the present note we compare existing and new practices for this index and offer recommendations on which to use.},
	language = {en},
	number = {2},
	urldate = {2022-04-06},
	journal = {Computer Physics Communications},
	author = {Saltelli, Andrea and Annoni, Paola and Azzini, Ivano and Campolongo, Francesca and Ratto, Marco and Tarantola, Stefano},
	month = feb,
	year = {2010},
	pages = {259--270},
	file = {Saltelli et al. - 2010 - Variance based sensitivity analysis of model outpu.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\E4IA9BBB\\Saltelli et al. - 2010 - Variance based sensitivity analysis of model outpu.pdf:application/pdf},
}

@article{gottsche_integrated_nodate,
	title = {An {Integrated} {Nuclear} {Archaeology} {Approach} to {Reconstructing} {Fissile} {Material} {Production} {Histories}},
	abstract = {Independent estimates assume that the world-wide civilian and military fissile material stocks amount to 500 tons of plutonium and 1,400 tons of highly-enriched uranium (HEU). To enable deep cuts in warhead arsenals, states will very likely need to verify declarations of fissile material stocks, as they could be used to build new nuclear weapons. One approach is nuclear archaeology, reconstructing the past production of those materials. Research has so far focused on specific measurements in reactors to assess past plutonium production, on deposits in gaseous diffusion plants and isotopics of depleted uranium tails to assess HEU production. For the large historical production of separated plutonium and HEU by Russia and the United States, uncertainties corresponding to large numbers of significant quantities remain with these techniques. A combination of measurements, fuel cycle simulations and reviews of records from past production activities could significantly reduce these uncertainties. This combination also would enable cross-checking information and measurement results for consistency. To demonstrate this approach, we conduct a case study. A declared production history is generated using the CYCLUS nuclear fuel cycle simulator. The simulation results are signatures resulting from the simulated history, some of which could in principle be measured. Assessing the isotopic compositions of waste streams, for example, can allow for cross-checking of declared fuel cycle histories. Based on this case study, the capabilities of the approach will be examined.},
	language = {en},
	author = {Göttsche, Malte and Mouginot, Baptiste},
	pages = {8},
	file = {Göttsche and Mouginot - An Integrated Nuclear Archaeology Approach to Reco.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\RZK6HAY9\\Göttsche and Mouginot - An Integrated Nuclear Archaeology Approach to Reco.pdf:application/pdf},
}

@article{smirnov_physical_2020,
	title = {Physical and {Technical} {Problems} of {Reprocessed} {Uranium} {Enrichment} with {Repeated} {Recycling} in {Light}-{Water} {Reactors} and {Ways} to {Solve} {Them}},
	volume = {128},
	issn = {1573-8205},
	url = {https://doi.org/10.1007/s10512-020-00681-9},
	doi = {10.1007/s10512-020-00681-9},
	abstract = {Issues concerning fuel cycle closure are discussed. It is shown that from the standpoint of full utilization of reprocessed nuclear materials the main problems are associated with repeated recycling of uranium, the reason being that limitations are imposed on the content of the isotope 232U in fresh fuel produced from reprocessed materials. The losses of the isotope 235U on repeated recycling of reprocessed uranium in the form of fuel from uranium regenerate and mixtures of processed uranium and plutonium oxides are evaluated. For a light-water reactor, a method of fuel cycle closure making it possible to reduce the 235U losses almost to zero on purification of reprocessed uranium from 232U is shown.},
	language = {en},
	number = {4},
	urldate = {2022-04-06},
	journal = {Atomic Energy},
	author = {Smirnov, A. Yu. and Gusev, V. E. and Sulaberidze, G. A. and Nevinitsa, V. A. and Bobrov, E. A. and Belov, I. A. and Rodionova, E. V.},
	month = aug,
	year = {2020},
	pages = {223--231},
	file = {Springer Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\8VPYIQUX\\Smirnov et al. - 2020 - Physical and Technical Problems of Reprocessed Ura.pdf:application/pdf},
}

@misc{us_nuclear_regulatory_commission_louisiana_2022,
	title = {Louisiana {Energy} {Services} ({LES})},
	url = {https://www.nrc.gov/info-finder/fc/urenco-enrichment-fac-nm-lc.html},
	urldate = {2022-04-06},
	author = {{U.S. Nuclear Regulatory Commission}},
	month = jan,
	year = {2022},
	note = {Publication Title: NRC Web},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\PPSKDR4X\\urenco-enrichment-fac-nm-lc.html:text/html},
}

@article{thiolliere_methodology_2018,
	title = {A methodology for performing sensitivity analysis in dynamic fuel cycle simulation studies applied to a {PWR} fleet simulated with the {CLASS} tool},
	volume = {4},
	copyright = {© N. Thiollière et al., published by EDP Sciences, 2018},
	issn = {2491-9292},
	url = {https://www.epj-n.org/articles/epjn/abs/2018/01/epjn170042/epjn170042.html},
	doi = {10.1051/epjn/2018009},
	abstract = {Fuel cycle simulators are used worldwide to provide scientific assessment to fuel cycle future strategies. Those tools help understanding the fuel cycle physics and determining the most impacting drivers at the cycle scale. A standard scenario calculation is usually based on a set of operational assumptions, such as reactor Burn-Up, deployment history, cooling time, etc. Scenario output is then the evolution of isotopes mass in the facilities that composes the nuclear fleet. The increase of computing capacities and the use of neutron data fast predictors provide new opportunities in nuclear scenario studies. Indeed, a very high number of calculations is possible, which allows testing a high number of operational assumptions combinations. The global sensitivity analysis (GSA) formalism is specifically well adapted for this kind of problem. In this new framework, a scenario study is based on the sampling of operational data, which become input variables. A first result of a scenario study is the highlight of relations between operational input data and outputs. Input variable subspace that satisfy optimization criteria on an output, such as plutonium incineration or stabilization, can also be determined. In this paper, a focus is made on the methodology based on GSA. This innovative methodology is presented and applied to a simple fleet simulation composed of a PWR-UOx fuel and a PWR-MOx fuel. Calculations are done with the fuel cycle simulator CLASS developed by the CNRS/IN2P3 in collaboration with IRSN. The design of experiment is built from five fuel cycle input sampled variables. Sensitivity indices have been calculated on plutonium and minor actinide (MA) production. It shows that the PWR-UOx Burn-Up and the fraction of PWR-MOx fuel are the most important input variables that explain the plutonium production. For the MA production, main drivers depend strongly on isotopes. Sensitivity analysis also reveals input variable subspace responsible of simulation crash, what led to an important improvement of the model algorithms. An equilibrium condition on the plutonium mass in the stockpile used for building MOx fuel has been applied. The solution is represented as a subspace in the PWR-UOx Burn-Up and PWR-MOx fraction input space. For instance, achieving a plutonium equilibrium in a stockpile fed by a PWR-UOx that operates at 40 GWd/t requires a PWR-MOx fraction between 9 and 14\%. This study also provides data related to plutonium incineration induced by the utilization of the MOx.},
	language = {en},
	urldate = {2022-04-04},
	journal = {EPJ Nuclear Sciences \& Technologies},
	author = {Thiollière, Nicolas and Clavel, Jean-Baptiste and Courtin, Fanny and Doligez, Xavier and Ernoult, Marc and Issoufou, Zakari and Krivtchik, Guillaume and Leniau, Baptiste and Mouginot, Baptiste and Bidaud, Adrien and David, Sylvain and Lebrin, Victor and Perigois, Carole and Richet, Yann and Somaini, Alice},
	year = {2018},
	pages = {13},
	annote = {Publisher: EDP Sciences},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\PPDKECNN\\PPDKECNN.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\5AFA5438\\epjn170042.html:text/html},
}

@techreport{keppler_nuclear_2015,
	address = {Nuclear Energy Agency of the OECD (NEA)},
	title = {Nuclear {Energy}: {Combating} {Climate} {Change}},
	shorttitle = {Nuclear {Energy}},
	abstract = {Global electricity demand is expected to increase strongly over the coming decades, even assuming much improved end-use efficiency Meeting this demand while drastically reducing CO\_2 emissions from the electricity sector will be a major challenge Given that the once-significant expectations placed on carbon capture and storage are rapidly diminishing, and given that hydropower resources are in limited supply, there are essentially only two options to de-carbonise an ever increasing electricity sector: nuclear power and renewable energy sources such as wind and solar PV Of these two options, only nuclear provides firmly dispatchable base-load electricity, since the variability of wind and solar PV requires flexible back-up that is frequently provided by carbon-intensive peak-load plants The declining marginal value of electricity production and the security of electricity supply are additional issues that must be taken into account Nuclear power plants do, however, face challenges due to their large up-front capital costs, complex project management requirements and difficulties in siting As technologies with high fixed costs, both nuclear power and renewables must respond to the challenge of acquiring long-term financing, since investments in capital-intensive low-carbon technologies are unlikely to be forthcoming in liberalised wholesale markets In order to substantially de-carbonise the electricity systems of OECD countries, policy-makers must understand the similarities, differences and complementarities between nuclear and renewables in the design of future low-carbon electricity systems The value of dispatchable low-carbon technologies, such as hydro and nuclear, for the safe and reliable functioning of electricity systems must also be recognised Should the de-carbonisation of electricity sectors in the wake of COP 21 become a reality, nuclear power might well be the single most important source of electricity by 2050, thanks mainly to the contribution of non-OECD countries COP 21 offers the opportunity to include nuclear energy firmly in future flexibility mechanisms such as the Clean Development Mechanism (CDM), or a potential successor in the post-2020 period, thus enabling nuclear full potential to reduce climate-change inducing greenhouse gas emissions To achieve this objective, however, it is important to understand the current and potential contribution of nuclear power in reducing future greenhouse gas emissions, as well as the appropriate measures that governments can take to address outstanding social, institutional and financial issues so as to ensure the necessary expansion of nuclear generating capacity that will make the 2 deg scenario a reality},
	author = {Keppler, Jan Horst and Paillere, Henri},
	year = {2015},
	pages = {19},
	annote = {NEA–7208 INIS Reference Number: 47009672},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\WZR5DZ9Y\\Keppler and Paillere - 2015 - Nuclear Energy Combating Climate Change.pdf:application/pdf},
}

@article{ternovykha_determination_2017,
	title = {Determination of equilibrium fuel composition for fast reactor in closed fuel cycle},
	volume = {153},
	copyright = {© The Authors, published by EDP Sciences, 2017},
	issn = {2100-014X},
	url = {https://www.epj-conferences.org/articles/epjconf/abs/2017/22/epjconf_icrs2017_07034/epjconf_icrs2017_07034.html},
	doi = {10.1051/epjconf/201715307034},
	abstract = {Technique of evaluation of multiplying and reactivity characteristics of fast reactor operating in the mode of multiple refueling is presented. We describe the calculation model of the vertical section of the reactor. Calculation validations of the possibility of correct application of methods and models are given. Results on the isotopic composition, mass feed, and changes in the reactivity of the reactor in closed fuel cycle are obtained. Recommendations for choosing perspective fuel compositions for further research are proposed.},
	language = {en},
	urldate = {2022-03-27},
	journal = {EPJ Web of Conferences},
	author = {Ternovykha, Mikhail and Tikhomirov, Georgy and Khomyakov, Yury and Suslov, Igor},
	year = {2017},
	pages = {07034},
	annote = {Publisher: EDP Sciences},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\LH8YH8M9\\Ternovykha et al. - 2017 - Determination of equilibrium fuel composition for .pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\JEI3PSSJ\\epjconf_icrs2017_07034.html:text/html},
}

@inproceedings{dahlberg_23_1975,
	title = {23. {Effects} of {U}-236 and other uranium isotopes on {HTGR} fuel cycle.},
	isbn = {978-0-7277-4445-6},
	url = {https://www.icevirtuallibrary.com/doi/abs/10.1680/uis.44456.0027},
	doi = {10.1680/uis.44456.0027},
	language = {eng},
	urldate = {2022-03-27},
	booktitle = {{URANIUM} {ISOTOPE} {SEPARATION}},
	publisher = {Thomas Telford Publishing},
	author = {Dahlberg, R. C.},
	month = jan,
	year = {1975},
	pages = {1--9},
	file = {Dahlberg - 1975 - 23. Effects of U-236 and other uranium isotopes on.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\QV4DYST6\\FTSGC7JA.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\CMZDF4DN\\uis.44456.html:text/html},
}

@techreport{james_advanced_1980,
	address = {Canada},
	title = {Advanced fuel cycles: a rationale and strategy for adopting the low-enriched-uranium fuel cycle},
	shorttitle = {Advanced fuel cycles},
	abstract = {A two-year study of alternatives to the natural uranium fuel cycle in CANDU reactors is summarized The possible advanced cycles are briefly described Selection criteria for choosing a cycle for development include resource utilization, economics, ease of implementaton, and social acceptability It is recommended that a detailed study should be made with a view to the early implementation of the low-enriched uranium cycle (LL)},
	author = {James, R.A.},
	year = {1980},
	pages = {28},
	annote = {OH–80009 INIS Reference Number: 11571815},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\ECIQQAHQ\\James - 1980 - Advanced fuel cycles a rationale and strategy for.pdf:application/pdf},
}

@article{kunsch_nuclear_1987,
	series = {First {EURO} {VII} special issue: {Location} and transportation problems production systems},
	title = {Nuclear fuel cycle optimization using multi-objective stochastic linear programming},
	volume = {31},
	issn = {0377-2217},
	url = {https://www.sciencedirect.com/science/article/pii/0377221787900282},
	doi = {10.1016/0377-2217(87)90028-2},
	abstract = {The share of electricity produced by nuclear power plants is still increasing in many countries. If the head-end of the nuclear fuel cycle, regarding all operations before leaving the reactor, has now reached maturity, many pathways are still possible in the back-end of the cycle, dealing with the spent fuel. The long-term consequences of any decision regarding subjects such as fuel reprocessing, waste disposal, etc., require the use of strategic planning methods, in which provision is made for multiple objectives and for uncertainties. An interactive multicriteria approach using stochastic linear programming is provided by the code Strange, which has already been applied to different energy strategy problems, also outside the nuclear field. The application presented in the paper illustrates the search for a best fuel cycle policy including four criteria: production costs, the supply of raw material, the commercial balance and employment. The concept of scenarios is used to describe future uncertainties.},
	language = {en},
	number = {2},
	urldate = {2022-03-27},
	journal = {European Journal of Operational Research},
	author = {Kunsch, P. L. and Teghem, J.},
	month = aug,
	year = {1987},
	keywords = {Optimization, nuclear fuel, multiple criteria},
	pages = {240--249},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\PQBN6Z73\\GNBG9VFX.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\4Y8335JE\\0377221787900282.html:text/html},
}

@article{zhou_economic_2014,
	title = {Economic analysis of two nuclear fuel cycle options},
	volume = {71},
	issn = {0306-4549},
	url = {https://www.sciencedirect.com/science/article/pii/S0306454914001777},
	doi = {10.1016/j.anucene.2014.04.005},
	abstract = {There are two major nuclear fuel cycle options in the world: the once-through cycle (OTC) option and the closed fuel cycle (CFC) option which consists of the thermal reactor recycle (TRR) and the fast reactor recycle (FRR). Presently, the TRR option has been industrially implemented in some European countries while the FRR option is still under development internationally. In this paper, the economic analysis of OTC and TRR options was carried out using levelized fuel cycle cost (LFCC). The two options were analyzed by calculating the equilibrium material flows as well as the economic costs of the overall fuel cycle components. The LFCCs of the two options were obtained as follows: OTC \$5.94±0.67mills/kWh and TRR \$6.13±0.55mills/kWh. Taking all uncertainties into considerations, the two options’ costs were in the same range. In addition, the sensitivity analysis was made to figure out the breakeven uranium price (\$112/kgHM), at which uranium price from OTC was economically competitive to TRR option slightly. Under the most possible international circumstance, it indicates a decreasing breakeven uranium price in future, which means TRR option would be more economical than OTC option.},
	language = {en},
	urldate = {2022-03-27},
	journal = {Annals of Nuclear Energy},
	author = {Zhou, Chaoran and Liu, Xuegang and Gu, Zhongmao and Wang, Yugang},
	month = sep,
	year = {2014},
	keywords = {Sensitivity, Breakeven price, Economics analysis, LFCC, Material flows, Nuclear fuel cycle option},
	pages = {230--236},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\JJ42IRQA\\Zhou et al. - 2014 - Economic analysis of two nuclear fuel cycle option.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\QPUNHEVL\\S0306454914001777.html:text/html},
}

@article{bunn_economics_2005,
	title = {The {Economics} of {Reprocessing} versus {Direct} {Disposal} of {Spent} {Nuclear} {Fuel}},
	volume = {150},
	issn = {0029-5450},
	url = {https://doi.org/10.13182/NT05-A3618},
	doi = {10.13182/NT05-A3618},
	abstract = {We assess the economics of reprocessing versus direct disposal of spent fuel. The uranium price at which reprocessing spent fuel from light water reactors (LWRs) and recycling the resulting plutonium and uranium in LWRs would become economic is estimated for a range of reprocessing prices and other fuel cycle costs. The contribution of both fuel cycle options to the cost of electricity is also estimated. A similar analysis is performed to compare fast neutron reactors (FRs) with LWRs. We review available information about various fuel cycle costs, as well as the quantities of uranium likely to be recoverable at a range of future prices. We conclude that the once-through LWR fuel cycle is likely to remain significantly cheaper than recycling in either LWRs or FRs for at least the next 50 yr, even with substantial growth in nuclear power.},
	number = {3},
	urldate = {2022-03-27},
	journal = {Nuclear Technology},
	author = {Bunn, Matthew and Holdren, John P. and Fetter, Steve and Van Der Zwaan, Bob},
	month = jun,
	year = {2005},
	pages = {209--230},
	annote = {Publisher: Taylor \& Francis \_eprint: https://doi.org/10.13182/NT05-A3618},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\HT96QUZR\\Bunn et al. - 2005 - The Economics of Reprocessing versus Direct Dispos.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\AL73TSDJ\\NT05-A3618.html:text/html},
}

@article{nevinitsa_fuel_2020,
	title = {Fuel cycle of light water reactor with full consumption of recycled uranium},
	volume = {85},
	issn = {2195-8580},
	url = {https://www.degruyter.com/document/doi/10.3139/124.200025/html},
	doi = {10.3139/124.200025},
	abstract = {The paper describes an approach to solve the problem of closing fuel cycle of light water reactors (LWR) trough the multiple uranium recycling. Since the second uranium recycle there is a problem of full return of the recycled uranium to LWR fuel cycle due to significant increasing of 232 U concentration and strong regulatory restrictions on its content. The paper shows that the use of a double cascade is able to provide almost complete return of recycled uranium to the fuel cycle with minor losses. The reason for the losses is the necessity to clean the recycled uranium from the 232 U isotope. We developed a multicriteria approach to choosing the optimal cascade scheme parameters. The efficiency of the algorithm is demonstrated by the example of enrichment of the recycled uranium of the second recycle. It is shown that not correctly selected optimization criteria of the double cascade enrichment scheme can lead to the fact that the loss of the 235 U isotope, provided with waste treatment from 232 U, will exceed its savings.},
	language = {de},
	number = {4},
	urldate = {2022-03-27},
	journal = {Kerntechnik},
	author = {Nevinitsa, Vladimir and Rodionova, Ekaterina and Smirnov, Andrey},
	month = apr,
	year = {2020},
	pages = {314--321},
	annote = {Publisher: De Gruyter},
}

@article{rodriguez-penalonga_review_2017,
	title = {A {Review} of the {Nuclear} {Fuel} {Cycle} {Strategies} and the {Spent} {Nuclear} {Fuel} {Management} {Technologies}},
	volume = {10},
	copyright = {http://creativecommons.org/licenses/by/3.0/},
	issn = {1996-1073},
	url = {https://www.mdpi.com/1996-1073/10/8/1235},
	doi = {10.3390/en10081235},
	abstract = {Nuclear power has been questioned almost since its beginnings and one of the major issues concerning its social acceptability around the world is nuclear waste management. In recent years, these issues have led to a rise in public opposition in some countries and, thus, nuclear energy has been facing even more challenges. However, continuous efforts in R\&D (research and development) are resulting in new spent nuclear fuel (SNF) management technologies that might be the pathway towards helping the environment and the sustainability of nuclear energy. Thus, reprocessing and recycling of SNF could be one of the key points to improve the social acceptability of nuclear energy. Therefore, the purpose of this paper is to review the state of the nuclear waste management technologies, its evolution through time and the future advanced techniques that are currently under research, in order to obtain a global vision of the nuclear fuel cycle strategies available, their advantages and disadvantages, and their expected evolution in the future.},
	language = {en},
	number = {8},
	urldate = {2022-03-27},
	journal = {Energies},
	author = {Rodríguez-Penalonga, Laura and Moratilla Soria, B. Yolanda},
	month = aug,
	year = {2017},
	keywords = {nuclear energy, nuclear waste management, recycling, reprocessing},
	pages = {1235},
	annote = {Number: 8 Publisher: Multidisciplinary Digital Publishing Institute},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\AHWUTQDN\\6VICLQGP.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\J7YU7RXX\\1235.html:text/html},
}

@article{fedorov_use_2005,
	title = {Use of {Recovered} {Uranium} and {Plutonium} in {Thermal} {Reactors}},
	volume = {99},
	issn = {1573-8205},
	url = {https://doi.org/10.1007/s10512-005-0248-9},
	doi = {10.1007/s10512-005-0248-9},
	abstract = {A possible version of the VVER-1000 fuel cycle without separation of uranium and plutonium during reprocessing of spent fuel is examined. In this fuel cycle, the uranium-plutonium regenerate obtained, from which other actinides and fission products have been removed, is used after enriched natural uranium is added for preparing VVER fuel. The results of a calculation of the content of uranium and plutonium isotopes in the spent uranium-plutonium fuel after one and two recycles in VVER-1000 are presented. The main advantages of the fuel cycle are discussed: lower risk of plutonium proliferation, savings of natural uranium, and less spent fuel as compared with an open uranium fuel cycle.},
	language = {en},
	number = {2},
	urldate = {2022-03-27},
	journal = {Atomic Energy},
	author = {Fedorov, Yu. S. and Bibichev, B. A. and Zil'berman, B. Ya. and Kudryavtsev, E. G.},
	month = aug,
	year = {2005},
	pages = {572--576},
	file = {Springer Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\UNV4HWDM\\Fedorov et al. - 2005 - Use of Recovered Uranium and Plutonium in Thermal .pdf:application/pdf},
}

@incollection{poinssot_2_2015,
	address = {Oxford},
	series = {Woodhead {Publishing} {Series} in {Energy}},
	title = {2 - {Role} of recycling in advanced nuclear fuel cycles},
	isbn = {978-1-78242-212-9},
	url = {https://www.sciencedirect.com/science/article/pii/B9781782422129000022},
	abstract = {This chapter describes the anticipated long-term evolutions of nuclear fuel cycles. The main driver for such evolution is the need for improving the sustainability of global energy systems. Indeed, sustainability is becoming the international reference approach to reconciling the different fields of analyses; that is, technical performance, economic viability, environmental preservation, and societal acceptance. While our societies have to face the issue of finding new energy models that help to mitigate climate change, global approaches are mandatory to select the relevant improvements for the different energy systems, including nuclear energy. After describing world energy issues, this chapter will detail the relevant criteria that could be used to assess the respective values of the different energy systems and will describe how nuclear energy could improve its contribution to sustainability by shifting toward a more efficient recycling, with different steps toward potential implementation.},
	language = {en},
	urldate = {2022-03-27},
	booktitle = {Reprocessing and {Recycling} of {Spent} {Nuclear} {Fuel}},
	publisher = {Woodhead Publishing},
	author = {Poinssot, Ch. and Boullis, B. and Bourg, S.},
	editor = {Taylor, Robin},
	month = jan,
	year = {2015},
	doi = {10.1016/B978-1-78242-212-9.00002-2},
	keywords = {Spent nuclear fuel, Reprocessing, Nuclear fuel cycle, Sustainability, Actinides recycling, Back-end of the fuel cycle, Uranium resource},
	pages = {27--48},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\FYFKNJX8\\Poinssot et al. - 2015 - 2 - Role of recycling in advanced nuclear fuel cyc.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\SKK3CXHI\\B9781782422129000022.html:text/html},
}

@techreport{ballery_nuclear_1995,
	address = {France},
	title = {The nuclear fuel cycle, an overview},
	abstract = {Because uranium is widely distributed on the face of the Earth, nuclear energy has a very large potential as an energy source in view of future depletion of fossil fuel reserves Also future energy requirements will be very sizeable as populations of developing countries are often growing and make the energy question one of the major challenges for the coming decades Today, nuclear contributes some 340 GWe to the energy requirements of the world Present and future nuclear programs require an adequate fuel cycle industry, from mining, refining, conversion, enrichment, fuel fabrication, fuel reprocessing and the storage of the resulting wastes The commercial fuel cycle activities amount to an annual business in the 7-8 billions of US Dollars in the hands of a large number of industrial operators This paper gives details about companies and countries involved in each step of the fuel cycle and about the national strategies and options chosen regarding the back end of the fuel cycle (waste storage and reprocessing) These options are illustrated by considering the policy adopted in three countries (France, United Kingdom, Japan) versed in reprocessing (JS) 13 figs, 2 tabs},
	author = {Ballery, J.L. and Cazalet, J. and Hagemann, R.},
	year = {1995},
	pages = {26},
	annote = {CEA-CONF–12183 INIS Reference Number: 27048708},
	file = {27048708.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\5UFBUYUV\\27048708.pdf:application/pdf;Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\X888F8UZ\\Ballery et al. - 1995 - The nuclear fuel cycle, an overview.pdf:application/pdf},
}

@techreport{shwageraus_optimization_2003,
	type = {Technical {Report}},
	title = {Optimization of the {LWR} {Nuclear} {Fuel} {Cycle} for {Minimum} {Waste} {Production}},
	url = {https://dspace.mit.edu/handle/1721.1/75166},
	abstract = {The once through nuclear fuel cycle adopted by the majority of countries with operating commercial power reactors imposes a number of concerns. The radioactive waste created in the once through nuclear fuel cycle has to be isolated from the environment for thousands of years. In addition, plutonium and other actinides, after the decay of fission products, could become targets for weapon proliferators. Furthermore, only a small fraction of the energy potential in the fuel is being used. All these concerns can be addressed if a closed fuel cycle strategy is considered offering the possibility for partitioning and transmutation of long lived radioactive waste, enhanced proliferation resistance, and improved utilization of natural resources. It is generally believed that dedicated advanced reactor systems have to be designed in order to perform the task of nuclear waste transmutation effectively. The development and deployment of such innovative systems is technically and economically challenging. In this work, a possibility of constraining the generation of long lived radioactive waste through multi-recycling of Trans-uranic actinides (TRU) in existing Light Water Reactors (LWR has been studied. Thorium based and fertile free fuels (FFF) were analyzed as the most attractive candidates for TRU burning in LWRs. Although both fuel types can destroy TRU at comparable rates (about 1150 kg/GWe-Year in FFF and up to 900 kg/GWe-Year in Th) and achieve comparable fractional TRU burnup (close to 50a/o), the Th fuel requires significantly higher neutron moderation than practically feasible in a typical LWR lattice to achieve such performance. On the other hand, the FFF exhibits nearly optimal TRU destruction performance in a typical LWR fuel lattice geometry. Increased TRU presence in LWR core leads to neutron spectrum hardening, which results in reduced control materials reactivity worth. The magnitude of this reduction is directly related to the amount of TRU in the core. A potential for positive void reactivity feedback limits the maximum TRU loading. Th and conventional mixed oxide (MOX) fuels require higher than FFF TRU loading to sustain a standard 18 fuel cycle length due to neutron captures in Th232 and U238 respectively. Therefore, TRU containing Th and U cores have lower control materials worth and greater potential for a positive void coefficient than FFF core. However, the significantly reduced fuel Doppler coefficient of the fully FFF loaded core and the lower delayed neutron fraction lead to questions about the FFF performance in reactivity initiated accidents. The Combined Non-Fertile and UO[subscript 2] (CONFU) assembly concept is proposed for multirecycling of TRU in existing PWRs. The assembly assumes a heterogeneous structure where about 20\% of the UO[subscript 2] fuel pins on the assembly periphery are replaced with FFF pins hosting TRU generated in the previous cycle. The possibility of achieving zero TRU net is demonstrated. The concept takes advantage of superior TRU destruction performance in FFF allowing minimization of TRU inventory. At the same time, the core physics is still dominated by UO[subscript 2] fuel allowing maintenance of core safety and control characteristics comparable to all-UO[subscript 2]. A comprehensive neutronic and thermal hydraulic analysis as well as numerical simulation of reactivity initiated accidents demonstrated the feasibility of TRU containing LWR core designs of various heterogeneous geometries. The power peaking and reactivity coefficients for the TRU containing heterogeneous cores are comparable to those of conventional UO[subscript 2] cores. Three to five TRU recycles are required to achieve an equilibrium fuel cycle length and TRU generation and destruction balance. A majority of TRU nuclides reach their equilibrium concentration levels in less than 20 recycles. The exceptions are Cm246, Cm248, and Cf252. Accumulation of these isotopes is highly undesirable with regards to TRU fuel fabrication and handling because they are very strong sources of spontaneous fission (SF) neutrons. Allowing longer cooling times of the spent fuel before reprocessing can drastically reduce the SF neutron radiation problem due to decay of Cm244 and Cf252 isotopes with particularly high SF source. Up to 10 TRU recycles are likely to be feasible if 20 years cooling time between recycles is adopted. Multi-recycling of TRU in the CONFU assembly reduces the relative fraction of fissile isotopes in the TRU vector from about 60\% in the initial spent UO[subscript 2] to about 25\% at equilibrium. As a result, the fuel cycle length is reduced by about 30\%. An increase in the enrichment of UO[subscript 2] pins from 4.2 to at least 5\% is required to compensate for the TRU isotopics degradation. The environmental impact of the sustainable CONFU assembly based fuel cycle is limited by the efficiency of TRU recovery in spent fuel reprocessing. TRU losses of 0.1\% from the CONFU fuel reprocessing ensure the CONFU fuel cycle radiotoxicity reduction to the level of corresponding amount of original natural uranium ore within 1000 years. The cost of the sustainable CONFU based fuel cycle is about 60\% higher than that of the once through UO[subscript 2] fuel cycle, whereas the difference in total cost of electricity between the two cycles is only 8\%. The higher fuel cycle cost is a result of higher uranium enrichment in a CONFU assembly required to compensate for the degradation of TRU isotopics and cost of reprocessing. The major expense in the sustainable CONFU fuel cycle is associated with the reprocessing of UO[subscript 2] fuel. Although reprocessing and fabrication of FFF pins have relatively high unit costs, their contribution to the fuel cycle cost is marginal as a result of the small TRU throughput. Reductions in the unit costs of UO[subscript 2] reprocessing and FFF fabrication by a factor of two would result in comparable fuel cycle costs for the CONFU and conventional once through cycle. An increase in natural uranium prices and waste disposal fees will also make the closed fuel cycle more economically attractive. Although, the cost of the CONFU sustainable fuel cycle is comparable to that of a closed cycle using a critical fast actinide burning reactor (ABR), the main advantage of the CONFU is the possibility of fast deployment, since it does not require as extensive development and demonstration as needed for fast reactors. The cost of the CONFU fuel cycle is projected to be considerably lower than that of a cycle with an accelerator driven fast burner system.},
	language = {en},
	urldate = {2022-03-27},
	institution = {Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program},
	author = {Shwageraus, Eugene and Hejzlar, Pavel and Kazimi, Mujid S.},
	month = oct,
	year = {2003},
	annote = {Accepted: 2012-12-03T19:47:00Z},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\BT9XTQWI\\75166.html:text/html},
}

@article{park_comparative_2011,
	series = {Asian {Energy} {Security}},
	title = {Comparative study of different nuclear fuel cycle options: {Quantitative} analysis on material flow},
	volume = {39},
	issn = {0301-4215},
	shorttitle = {Comparative study of different nuclear fuel cycle options},
	url = {https://www.sciencedirect.com/science/article/pii/S0301421511002801},
	doi = {10.1016/j.enpol.2011.03.083},
	abstract = {As a nation develops its nuclear strategies, it must consider various aspects of nuclear energy such as sustainability, environmental-friendliness, proliferation-resistance, economics, technologies, and so on. A nuclear fuel cycle study could give convincing answers to many questions in regard to technical aspects. However, one nuclear fuel cycle option cannot be superior in all aspects. Therefore a nation must identify its top priority and accordingly evaluate all the possible nuclear fuel cycle options. For such a purpose, this paper examined four different fuel cycle options that are likely to be plausible under situation of Republic of Korea: once-through cycle, DUPIC recycling, thermal recycling using MOX fuel in PWR (pressurized water reactor), and SFR (sodium cooled fast reactor) employing fuel recycling by a pyroprocess. The options have been quantitatively compared in terms of resource utilization and waste generation based on 1TWh electricity production at a “steady-state” condition as a basic analysis. This investigation covered from the front-end of the fuel cycles to the final disposal and showed that the Pyro-SFR recycling appears to be the most competitive from these material quantitative aspects due to the reduction of the required uranium resources and the least amount of waste generation.},
	language = {en},
	number = {11},
	urldate = {2022-03-27},
	journal = {Energy Policy},
	author = {Park, Byung Heung and Gao, Fanxing and Kwon, Eun-ha and Ko, Won Il},
	month = nov,
	year = {2011},
	keywords = {Nuclear fuel cycle, Comparative study, Material flow analysis},
	pages = {6916--6924},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\KEL3HVS6\\7KHI2KD8.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\PZ57Z3FU\\S0301421511002801.html:text/html},
}

@techreport{rooney_system_2013,
	type = {Working {Paper}},
	title = {A {System} {Dynamics} {Study} of {Uranium} and the {Nuclear} {Fuel} {Cycle}},
	copyright = {All Rights Reserved},
	url = {https://www.repository.cam.ac.uk/handle/1810/244764},
	abstract = {To advance current knowledge of the uranium market, a system dynamics model of the nuclear fuel cycle for the time period 1988 to 2048 has been developed. The proposed framework of analysis illustrates some of the key features of the market for this commodity, including the role that time lags play in the formation of price volatility. Various demand reduction and substitution strategies and technologies are explored, and potential external shocks are simulated to investigate how price and the associated industry respond. Sensitivity analysis performed by considering key model parameters indicates that the time constant related to the formation of traders’ expectations of future market prices embedded in the proposed price discovery mechanism has a strong influence on both the amplitude and frequency of price peaks. One particularly interesting and timely scenario simulated is the possibility of the ending of the “Megatons to Megawatts” program, in which the USA agreed to buy down-blended uranium from former Soviet nuclear warheads for use in power production. This agreement has not been formally renewed and we find that in the absence of new substitute sources this could cause a significant rise in uranium prices. Finally, our analysis leads us to believe that uranium resource scarcity will not pose any significant challenges until the second half of the twenty first century at the earliest, even if high uranium demand projections are realized.},
	language = {en},
	urldate = {2022-03-27},
	institution = {Faculty of Economics},
	author = {Rooney, Matthew and Nuttall, William J. and Kazantzis, Nikolas},
	month = may,
	year = {2013},
	doi = {10.17863/CAM.5347},
	annote = {Accepted: 2013-07-30T14:16:40Z},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\56IXDLUT\\Rooney et al. - 2013 - A System Dynamics Study of Uranium and the Nuclear.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\AHLLT9Z7\\244764.html:text/html},
}

@article{fukuda_feasibility_2008,
	title = {Feasibility of {Reprocessed} {Uranium} in {LWR} {Fuel} {Cycle} for {Protected} {Plutonium} {Production}},
	volume = {45},
	issn = {0022-3131},
	url = {https://www.tandfonline.com/doi/abs/10.1080/18811248.2008.9711887},
	doi = {10.1080/18811248.2008.9711887},
	abstract = {Protected plutonium production (PPP) is an intrinsic measure to enhance the proliferation resistance of Pu by raising the 238Pu isotopic concentration, which denatures Pu on account of the high spontaneous fission neutron (SFN) rate and large decay heat (DH). This study is aimed at examining the feasibility of reprocessed uranium (RepU) with or without the addition of minor actinide (MA) in LWR fuel cycle for PPP and to make a tentative economic assessment of RepU possessing the PPP feature. It was analytically clarified that RepU enriched to 5\% 235U by centrifugation produced denatured Pu at higher burnup than about 40GWd/t. By the addition of more than 0.5\% MA to RepU and natural uranium both enriched to 5\%, Pu generated in the uranium fuel with MA added could be denatured up to 40 GWd/t at least. A diagram designed with functions of SFN rate and DH explicated the PPP features of re-enriched RepU and enriched natural uranium with or without MA addition. The economic assessment indicated that the cost of fuel cycle applying re-enriched RepU would be comparable to that of the conventional fuel cycle, if the cost of the source RepU is low. In addition, the LWR fuel cycle applying RepU for PPP was discussed.},
	number = {10},
	urldate = {2022-03-27},
	journal = {Journal of Nuclear Science and Technology},
	author = {FUKUDA, Kosaku and SAGARA, Hiroshi and SAITO, Masaki and MITSUHASHIY, Tsunetomo},
	month = oct,
	year = {2008},
	keywords = {reprocessed uranium, proliferation resistance, fuel cycle, LWR, centrifuge, cost assessment, feasibility, minor actinides, protected plutonium production, re-enrichment},
	pages = {1016--1027},
	annote = {Publisher: Taylor \& Francis \_eprint: https://www.tandfonline.com/doi/pdf/10.1080/18811248.2008.9711887},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\3HQENQ72\\FUKUDA et al. - 2008 - Feasibility of Reprocessed Uranium in LWR Fuel Cyc.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\LYTXMWUC\\18811248.2008.html:text/html},
}

@article{mccombie_key_2010,
	title = {The key role of the back-end in the nuclear fuel cycle},
	volume = {139},
	issn = {0011-5266},
	url = {https://doi.org/10.1162/daed.2010.139.1.32},
	doi = {10.1162/daed.2010.139.1.32},
	number = {1},
	urldate = {2022-03-27},
	journal = {Daedalus},
	author = {McCombie, Charles and Isaacs, Thomas},
	month = jan,
	year = {2010},
	pages = {32--43},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\W35TCHYA\\6NEEKEWM.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\FS4NCU23\\The-key-role-of-the-back-end-in-the-nuclear-fuel.html:text/html},
}

@article{knapp_potential_2010,
	series = {Energy {Efficiency} {Policies} and {Strategies} with regular papers.},
	title = {The potential of fission nuclear power in resolving global climate change under the constraints of nuclear fuel resources and once-through fuel cycles},
	volume = {38},
	issn = {0301-4215},
	url = {https://www.sciencedirect.com/science/article/pii/S0301421510005161},
	doi = {10.1016/j.enpol.2010.06.052},
	abstract = {Nuclear fission is receiving new attention as a developed source of carbon-free energy. A much larger number of nuclear reactors would be needed for a major impact on carbon emission. The crucial question is whether it can be done without increasing the risk of nuclear proliferation. Specifically, can a larger nuclear share in world energy production, well above the present 6\%, be achieved in the next few decades without adding the proliferation-sensitive technologies of reprocessing spent fuel and recycling plutonium to the problems of the unavoidable use of enrichment technology? The answer depends on the available uranium resources. We first looked for the maximum possible nuclear build-up in the 2025–2065 period under the constraints of the estimated uranium resources and the use of once-through nuclear fuel technology. Our results show that nuclear energy without reprocessing could reduce carbon emission by 39.6\% of the total reduction needed to bring the WEO 2009 Reference Scenario prediction of total GHG emissions in 2065 to the level of the WEO 450 Scenario limiting global temperature increase to 2°C. The less demanding strategy of the nuclear replacement of all non-CCS coal power plants retiring during the 2025–2065 period would reduce emission by 26.1\%.},
	language = {en},
	number = {11},
	urldate = {2022-03-27},
	journal = {Energy Policy},
	author = {Knapp, Vladimir and Pevec, Dubravko and Matijević, Mario},
	month = nov,
	year = {2010},
	keywords = {Global warming, Proliferation safety, Uranium resources},
	pages = {6793--6803},
	file = {ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\SD447RE2\\S0301421510005161.html:text/html},
}

@article{taebi_recycle_2008,
	title = {To {Recycle} or {Not} to {Recycle}? {An} {Intergenerational} {Approach} to {Nuclear} {Fuel} {Cycles}},
	volume = {14},
	issn = {1471-5546},
	shorttitle = {To {Recycle} or {Not} to {Recycle}?},
	url = {https://doi.org/10.1007/s11948-007-9049-y},
	doi = {10.1007/s11948-007-9049-y},
	abstract = {This paper approaches the choice between the open and closed nuclear fuel cycles as a matter of intergenerational justice, by revealing the value conflicts in the production of nuclear energy. The closed fuel cycle improve sustainability in terms of the supply certainty of uranium and involves less long-term radiological risks and proliferation concerns. However, it compromises short-term public health and safety and security, due to the separation of plutonium. The trade-offs in nuclear energy are reducible to a chief trade-off between the present and the future. To what extent should we take care of our produced nuclear waste and to what extent should we accept additional risks to the present generation, in order to diminish the exposure of future generation to those risks? The advocates of the open fuel cycle should explain why they are willing to transfer all the risks for a very long period of time (200,000 years) to future generations. In addition, supporters of the closed fuel cycle should underpin their acceptance of additional risks to the present generation and make the actual reduction of risk to the future plausible.},
	language = {en},
	number = {2},
	urldate = {2022-03-27},
	journal = {Science and Engineering Ethics},
	author = {Taebi, Behnam and Kloosterman, Jan Leen},
	month = jun,
	year = {2008},
	pages = {177--200},
	file = {Springer Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\SQB8Y2PR\\Taebi and Kloosterman - 2008 - To Recycle or Not to Recycle An Intergenerational.pdf:application/pdf},
}

@article{rothwell_sustainability_2014,
	series = {Nuclear {Energy} and {Sustainable} {Development}: {Selected} {Topics}},
	title = {Sustainability of light water reactor fuel cycles},
	volume = {74},
	issn = {0301-4215},
	url = {https://www.sciencedirect.com/science/article/pii/S0301421514004467},
	doi = {10.1016/j.enpol.2014.07.018},
	abstract = {This paper compares the sustainability of two light water reactor, LWR, fuel cycles: the once-through UOX (low-enriched uranium oxide) cycle and the twice-through MOX (Mixed Uranium-Plutonium Oxide) cycle (increasing the input efficiency of available uranium) by assessing their probable long-term competitiveness. With the retirement of diffusion enrichment facilities, enrichment prices have declined by one-third since 2009 and are likely to remain below \$100-kgSWU for the foreseeable future. Here, initial uranium prices are set at \$90/kgU and reprocessing costs at \$2500 per kilogram of heavy-metal throughput, representative of “new-build” costs for reprocessing facilities. Substantial reprocessing cost reductions must be achieved if MOX is to be competitive, i.e., if it is to improve the sustainability of the LWR. However, results indicate that preserving the MOX alternative for spent fuel management later in this century has a large present value under several sets of assumptions regarding uranium price increases and reprocessing cost decreases.},
	language = {en},
	urldate = {2022-03-27},
	journal = {Energy Policy},
	author = {Rothwell, Geoffrey and Wood, Thomas W. and Daly, Don and Weimar, Mark R.},
	month = dec,
	year = {2014},
	keywords = {Uranium, Light water reactors, Plutonium},
	pages = {S16--S23},
	file = {ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\QUYTAEHF\\S0301421514004467.html:text/html},
}

@article{shadrin_comparison_2016,
	title = {Comparison of {Closed} {Nuclear} {Fuel} {Cycle} {Technologies}},
	volume = {121},
	issn = {1573-8205},
	url = {https://doi.org/10.1007/s10512-016-0171-2},
	doi = {10.1007/s10512-016-0171-2},
	abstract = {The aim of this work is to compare different approaches to nuclear fuel cycle closure from the standpoint of plutonium utilization, fuel type, and reprocessing technology. It is shown that the choice of mixed uraniumplutonium nitride fuel for fast reactors will make it possible to effectively close the NFC and at the same time develope safe nuclear power; the combined (pyrochemical + hydro) technology will make it possible to reprocess any type of high-burnup short-decayed irradiated fuel from fast reactors and to obtain the final uranium-plutonium-neptunium product suitable for use in any fuel production technology.},
	language = {en},
	number = {2},
	urldate = {2022-03-27},
	journal = {Atomic Energy},
	author = {Shadrin, A. Yu. and Ivanov, V. B. and Skupov, M. V. and Troyanov, V. M. and Zherebtsov, A. A.},
	month = dec,
	year = {2016},
	pages = {119--126},
	file = {Springer Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\CYNNZAU5\\RHI2H7AR.pdf:application/pdf},
}

@article{poinssot_assessment_2014,
	title = {Assessment of the environmental footprint of nuclear energy systems. {Comparison} between closed and open fuel cycles},
	volume = {69},
	issn = {0360-5442},
	url = {https://www.sciencedirect.com/science/article/pii/S0360544214002035},
	doi = {10.1016/j.energy.2014.02.069},
	abstract = {Energy perspectives for the current century are dominated by the anticipated significant increase of energy needs. Particularly, electricity consumption is anticipated to increase by a factor higher than two before 2050. Energy choices are considered as structuring political choices that implies a long-standing and stable policy based on objective criteria. LCA (life cycle analysis) is a structured basis for deriving relevant indicators which can allow the comparison of a wide range of impacts of different energy sources. Among the energy-mix, nuclear power is anticipated to have very low GHG-emissions. However, its viability is severely addressed by the public opinion after the Fukushima accident. Therefore, a global LCA of the French nuclear fuel cycle was performed as a reference model. Results were compared in terms of impact with other energy sources. It emphasized that the French nuclear energy is one of the less impacting energy, comparable with renewable energy. In a second, part, the French scenario was compared with an equivalent open fuel cycle scenario. It demonstrates that an open fuel cycle would require about 16\% more natural uranium, would have a bigger environmental footprint on the “non radioactive indicators” and would produce a higher volume of high level radioactive waste.},
	language = {en},
	urldate = {2022-03-27},
	journal = {Energy},
	author = {Poinssot, Ch. and Bourg, S. and Ouvrier, N. and Combernoux, N. and Rostaing, C. and Vargas-Gonzalez, M. and Bruno, J.},
	month = may,
	year = {2014},
	keywords = {Nuclear energy, Environmental impacts, Energy system assessment, French nuclear fuel cycle, Life cycle analysis, Sustainable energy development},
	pages = {199--211},
	file = {ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\DSJXJTJ3\\S0360544214002035.html:text/html},
}

@article{myasoedov_nuclear_2016,
	title = {Nuclear fuel cycle and its impact on the environment},
	volume = {54},
	issn = {1556-1968},
	url = {https://doi.org/10.1134/S0016702916130115},
	doi = {10.1134/S0016702916130115},
	abstract = {In this paper, we consider the present-day situation and outlooks of the development of nuclear power generation in Russia and other countries. It was noted that the implementation of the concept of a closed nuclear-fuel cycle accepted in Russia relies on the solution of the problem of the disposal of spent nuclear fuel (SNF) and radioactive waste (RAW). This paper presents the main results of investigations focused on the development of radiation-safe methods of manufacturing nuclear fuel elements, including mixed uranium–plutonium oxide fuel for fast-neutron reactors; creation of low waste-production technologies of SNF processing and RAW disposal; and the analysis of fundamental features of the behavior and speciation of radionuclides in environmental objects for the development of efficient methods of radioecological monitoring and remediation of radionuclide-contaminated areas.},
	language = {en},
	number = {13},
	urldate = {2022-03-27},
	journal = {Geochemistry International},
	author = {Myasoedov, B. F. and Kalmykov, S. N. and Kulyako, Yu. M. and Vinokurov, S. E.},
	month = dec,
	year = {2016},
	pages = {1156--1167},
	file = {Springer Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\6I6DC9Z3\\Myasoedov et al. - 2016 - Nuclear fuel cycle and its impact on the environme.pdf:application/pdf},
}

@techreport{bays_technology_2010,
	title = {Technology {Insights} and {Perspectives} for {Nuclear} {Fuel} {Cycle} {Concepts}},
	url = {https://www.osti.gov/biblio/1004232},
	abstract = {The following report provides a rich resource of information for exploring fuel cycle characteristics. The most noteworthy trends can be traced back to the utilization efficiency of natural uranium resources. By definition, complete uranium utilization occurs only when all of the natural uranium resource can be introduced into the nuclear reactor long enough for all of it to undergo fission. Achieving near complete uranium utilization requires technologies that can achieve full recycle or at least nearly full recycle of the initial natural uranium consumed from the Earth. Greater than 99\% of all natural uranium is fertile, and thus is not conducive to fission. This fact requires the fuel cycle to convert large quantities of non-fissile material into fissile transuranics. Step increases in waste benefits are closely related to the step increase in uranium utilization going from non-breeding fuel cycles to breeding fuel cycles. The amount of mass requiring a disposal path is tightly coupled to the quantity of actinides in the waste stream. Complete uranium utilization by definition means that zero (practically, near zero) actinide mass is present in the waste stream. Therefore, fuel cycles with complete (uranium and transuranic) recycle discharge predominately fission products with some actinide process losses. Fuel cycles without complete recycle discharge a much more massive waste stream because only a fraction of the initial actinide mass is burned prior to disposal. In a nuclear growth scenario, the relevant acceptable frequency for core damage events in nuclear reactors is inversely proportional to the number of reactors deployed in a fuel cycle. For ten times the reactors in a fleet, it should be expected that the fleet-average core damage frequency be decreased by a factor of ten. The relevant proliferation resistance of a fuel cycle system is enhanced with: decreasing reliance on domestic fuel cycle services, decreasing adaptability for technology misuse, enablement of material accountability, and decreasing material attractiveness.},
	language = {English},
	number = {INL/EXT-10-19977},
	urldate = {2022-03-27},
	institution = {Idaho National Lab. (INL), Idaho Falls, ID (United States)},
	author = {Bays, S. and Piet, S. and Soelberg, N. and Lineberry, M. and Dixon, B.},
	month = sep,
	year = {2010},
	doi = {10.2172/1004232},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\TWI6E3M3\\Bays et al. - 2010 - Technology Insights and Perspectives for Nuclear F.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\SJ3I72JP\\1004232.html:text/html},
}

@article{ewing_nuclear_2008,
	title = {Nuclear {Fuel} {Cycle}: {Environmental} {Impact}},
	volume = {33},
	issn = {1938-1425},
	shorttitle = {Nuclear {Fuel} {Cycle}},
	url = {https://doi.org/10.1557/mrs2008.68},
	doi = {10.1557/mrs2008.68},
	abstract = {Every energy source has environmental impacts—positive and negative. Nuclear power is a carbon-free source of energy that can reduce CO2 emissions by displacing the use of fossil fuels. The present level of carbon displacement is approximately 0.5 gigatonnes of carbon per year (GtC/year), compared to the nearly 8 GtC/year emitted by the use of fossil fuels. However, there are three major negative environmental impacts of nuclear power: catastrophic accidents, nuclear weapons, and nuclear waste. The last two, weapons and waste, are directly tied to the type of nuclear fuel cycle (Figure 4 in the main nuclear article by Raj et al. in this issue). The different fuel cycles refect different strategies for the utilization of fssile nuclides, mainly 235U and 239Pu, and these different strategies have important implications for nuclear waste management and nuclear weapons proliferation.},
	language = {en},
	number = {4},
	urldate = {2022-03-27},
	journal = {MRS Bulletin},
	author = {Ewing, Rodney C.},
	month = apr,
	year = {2008},
	pages = {338--340},
	file = {Springer Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\2848V42E\\Ewing - 2008 - Nuclear Fuel Cycle Environmental Impact.pdf:application/pdf},
}

@article{schneider_measures_2013,
	title = {Measures of the environmental footprint of the front end of the nuclear fuel cycle},
	volume = {40},
	issn = {0140-9883},
	url = {https://www.sciencedirect.com/science/article/pii/S0140988313000042},
	doi = {10.1016/j.eneco.2013.01.002},
	abstract = {Previous estimates of environmental impacts associated with the front end of the nuclear fuel cycle (FEFC) have focused primarily on energy consumption and CO2 emissions. Results have varied widely. This work builds upon reports from operating facilities and other primary data sources to build a database of front end environmental impacts. This work also addresses land transformation and water withdrawals associated with the processes of the FEFC. These processes include uranium extraction, conversion, enrichment, fuel fabrication, depleted uranium disposition, and transportation. To allow summing the impacts across processes, all impacts were normalized per tonne of natural uranium mined as well as per MWh(e) of electricity produced, a more conventional unit for measuring environmental impacts that facilitates comparison with other studies. This conversion was based on mass balances and process efficiencies associated with the current once-through LWR fuel cycle. Total energy input is calculated at 8.7×10−3 GJ(e)/MWh(e) of electricity and 5.9×10−3 GJ(t)/MWh(e) of thermal energy. It is dominated by the energy required for uranium extraction, conversion to fluoride compound for subsequent enrichment, and enrichment. An estimate of the carbon footprint is made from the direct energy consumption at 1.7kg CO2/MWh(e). Water use is likewise dominated by requirements of uranium extraction, totaling 154L/MWh(e). Land use is calculated at 8×10−3m2/MWh(e), over 90\% of which is due to uranium extraction. Quantified impacts are limited to those resulting from activities performed within the FEFC process facilities (i.e. within the plant gates). Energy embodied in material inputs such as process chemicals and fuel cladding is identified but not explicitly quantified in this study. Inclusion of indirect energy associated with embodied energy as well as construction and decommissioning of facilities could increase the FEFC energy intensity estimate by a factor of up to 2.},
	language = {en},
	urldate = {2022-03-27},
	journal = {Energy Economics},
	author = {Schneider, E. and Carlsen, B. and Tavrides, E. and van der Hoeven, C. and Phathanapirom, U.},
	month = nov,
	year = {2013},
	keywords = {Nuclear fuel cycle, Environmental impacts},
	pages = {898--910},
	file = {ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\NJWFZT9Y\\S0140988313000042.html:text/html;Submitted Version:C\:\\Users\\abachmann\\Zotero\\storage\\I9SK89JA\\Schneider et al. - 2013 - Measures of the environmental footprint of the fro.pdf:application/pdf},
}

@article{brown_impact_2017,
	title = {Impact of thermal spectrum small modular reactors on performance of once-through nuclear fuel cycles with low-enriched uranium},
	volume = {101},
	issn = {0306-4549},
	url = {https://www.sciencedirect.com/science/article/pii/S0306454916306843},
	doi = {10.1016/j.anucene.2016.11.003},
	abstract = {Small modular reactors (SMRs) may offer potential benefits relative to large light water reactors, such as enhanced flexibility in deployment and operation. However, it is vital to understand the holistic impact of SMRs on nuclear fuel cycle performance. The focus of this paper is the fuel cycle impacts of light water SMRs in a once-through fuel cycle with low-enriched uranium fuel. A key objective of this paper is to describe preliminary neutronics and fuel cycle analyses conducted in support of the US Department of Energy, Office of Nuclear Energy, Fuel Cycle Options Campaign. The hypothetical light water SMR example case considered in these preliminary scoping studies is a “cartridge type” one-batch core with slightly less than 5.0\% enrichment. The high-level issues identified and preliminary scoping calculations in this paper are intended to inform decision makers regarding potential fuel cycle impacts of one-batch thermal-spectrum SMRs. In particular, this paper highlights the impact of increased neutron leakage and a reduced number of batches on the achievable burnup of the reactor. Fuel cycle performance metrics for the simplified example SMR analyzed herein are compared with those for a conventional three-batch light water reactor (LWR) in the following areas: nuclear waste management, environmental impact, and resource utilization. The metrics performance for such an SMR is degraded for the mass of spent nuclear fuel and high-level waste disposed of per energy generated, mass of depleted uranium disposed of per energy generated, land use per energy generated, and carbon emissions per energy generated. Finally, it is noted that the features of some SMR designs impact three main aspects of fuel cycle performance: (1) small cores, which mean high leakage (there is a radial and an axial component); (2) a heterogeneous core and extensive use of control rods and burnable poisons; and (3) single-batch cores. But not all SMR designs have all of these traits. The approach used in this study is an example bounding case, and not all SMRs may be impacted to the same extent.},
	language = {en},
	urldate = {2022-03-27},
	journal = {Annals of Nuclear Energy},
	author = {Brown, Nicholas R. and Worrall, Andrew and Todosow, Michael},
	month = mar,
	year = {2017},
	keywords = {Fuel cycle performance, Evaluation and screening, Neutron leakage, Small modular reactor},
	pages = {166--173},
	file = {ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\UGG5JQAN\\S0306454916306843.html:text/html;Submitted Version:C\:\\Users\\abachmann\\Zotero\\storage\\VWNETP7J\\Brown et al. - 2017 - Impact of thermal spectrum small modular reactors .pdf:application/pdf},
}

@article{ko_economic_2012,
	title = {Economic {Analysis} of {Different} {Nuclear} {Fuel} {Cycle} {Options}},
	volume = {2012},
	issn = {1687-6075},
	url = {https://www.hindawi.com/journals/stni/2012/293467/},
	doi = {10.1155/2012/293467},
	abstract = {An economic analysis has been performed to compare four nuclear fuel cycle options: a once-through cycle (OT), DUPIC recycling, thermal recycling using MOX fuel in a pressurized water reactor (PWR-MOX), and sodium fast reactor recycling employing pyroprocessing (Pyro-SFR). This comparison was made to suggest an economic competitive fuel cycle for the Republic of Korea. The fuel cycle cost (FCC) has been calculated based on the equilibrium material flows integrated with the unit cost of the fuel cycle components. The levelized fuel cycle costs (LFCC) have been derived in terms of mills/kWh for a fair comparison among the FCCs, and the results are as follows: OT 7.35 mills/kWh, DUPIC 9.06 mills/kWh, PUREX-MOX 8.94 mills/kWh, and Pyro-SFR 7.70 mills/kWh. Due to unavoidable uncertainties, a cost range has been applied to each unit cost, and an uncertainty study has been performed accordingly. A sensitivity analysis has also been carried out to obtain the break-even uranium price (215\$/kgU) for the Pyro-SFR against the OT, which demonstrates that the deployment of the Pyro-SFR may be economical in the foreseeable future. The influence of pyrotechniques on the LFCC has also been studied to determine at which level the potential advantages of Pyro-SFR can be realized.},
	language = {en},
	urldate = {2022-03-27},
	journal = {Science and Technology of Nuclear Installations},
	author = {Ko, Won Il and Gao, Fanxing},
	month = jun,
	year = {2012},
	pages = {e293467},
	annote = {Publisher: Hindawi},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\UPL2U7RT\\293467.html:text/html},
}

@book{hore-lacy_uranium_2016,
	title = {Uranium for {Nuclear} {Power}: {Resources}, {Mining} and {Transformation} to {Fuel}},
	isbn = {978-0-08-100333-6},
	shorttitle = {Uranium for {Nuclear} {Power}},
	abstract = {Uranium for Nuclear Power: Resources, Mining and Transformation to Fuel discusses the nuclear industry and its dependence on a steady supply of competitively priced uranium as a key factor in its long-term sustainability. A better understanding of uranium ore geology and advances in exploration and mining methods will facilitate the discovery and exploitation of new uranium deposits. The practice of efficient, safe, environmentally-benign exploration, mining and milling technologies, and effective site decommissioning and remediation are also fundamental to the public image of nuclear power. This book provides a comprehensive review of developments in these areas. Provides researchers in academia and industry with an authoritative overview of the front end of the nuclear fuel cycle Presents a comprehensive and systematic coverage of geology, mining, and conversion to fuel, alternative fuel sources, and the environmental and social aspects Written by leading experts in the field of nuclear power, uranium mining, milling, and geological exploration who highlight the best practices needed to ensure environmental safety},
	language = {en},
	publisher = {Woodhead Publishing},
	author = {Hore-Lacy, Ian},
	month = feb,
	year = {2016},
	keywords = {Technology \& Engineering / Power Resources / Nuclear},
	annote = {Google-Books-ID: U8PlBwAAQBAJ},
}

@article{waris_characteristics_2001,
	title = {Characteristics of {Several} {Equilibrium} {Fuel} {Cycles} of {PWR}},
	volume = {38},
	issn = {0022-3131},
	url = {https://doi.org/10.1080/18811248.2001.9715062},
	doi = {10.1080/18811248.2001.9715062},
	abstract = {This paper evaluated the influence of neutron spectrum on characteristics of several equilibrium fuel cycles of pressurized water reactor (PWR). In this study, five kinds of fuel cycles were investigated. Required uranium enrichment, required natural uranium amount, and toxicity of heavy metals (HMs) in spent fuel were presented for comparison. The results showed that the enrichment and the required amount of natural uranium decrease significantly with increasing number of confined heavy nuclides when uranium is discharged from the reactor. On the other hand, when uranium is totally confined, the enrichment becomes extremely high. The confinement of plutonium and minor actinides (MA) seems effective in reducing radio-toxicity of discharged wastes. By confining all heavy nuclides except uranium those three characteristics could be reduced considerably. For this fuel cycle the toxicity of HMs in spent fuel become nearly equal to or less than that of loaded uranium.},
	number = {7},
	urldate = {2022-03-27},
	journal = {Journal of Nuclear Science and Technology},
	author = {WARIS, Abdul and SEKIMOTO, Hiroshi},
	month = jul,
	year = {2001},
	keywords = {heavy metals, radiotoxicity, minor actinides, equilibrium fuel cycle, importance, neutron spectrum, plutonium, PWR type reactors, required natural uranium, spent fuels, uranium enrichment},
	pages = {517--526},
	annote = {Publisher: Taylor \& Francis \_eprint: https://doi.org/10.1080/18811248.2001.9715062},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\CTFB7ZAH\\WARIS and SEKIMOTO - 2001 - Characteristics of Several Equilibrium Fuel Cycles.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\LXDV2SFH\\18811248.2001.html:text/html},
}

@article{olander_theory_1981,
	title = {The theory of uranium enrichment by the gas centrifuge},
	volume = {8},
	issn = {0149-1970},
	url = {https://www.sciencedirect.com/science/article/pii/0149197081900263},
	doi = {10.1016/0149-1970(81)90026-3},
	abstract = {Onsager's analysis of the hydrodynamics of fluid circulation in the boundary layer on the rotor wall of a gas centrifuge is reviewed. The description of the flow in the boundary layers on the top and bottom end caps due to Carrier and Maslen is summarized. The method developed by Wood and Morton of coupling the flow models in the rotor wall and end cap boundary layers to complete the hydrodynamic analysis of the centrifuge is presented. Mechanical and thermal methods of driving the internal gas circulation are described. The isotope enrichment which results from the superposition of the elementary separation effect due to the centrifugal field in the gas and its internal circulation is analyzed by the Onsager-Cohen theory. The performance function representing the optimized separative power of a centrifuge as a function of throughput and cut is calculated for several simplified internal flow models. The use of asymmetric ideal cascades to exploit the distinctive features of centrifuge performance functions is illustrated.},
	language = {en},
	number = {1},
	urldate = {2022-03-27},
	journal = {Progress in Nuclear Energy},
	author = {Olander, Donald R.},
	month = jan,
	year = {1981},
	pages = {1--33},
	file = {ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\SMXYP5EN\\0149197081900263.html:text/html;Submitted Version:C\:\\Users\\abachmann\\Zotero\\storage\\BW5JBLCD\\Olander - 1981 - The theory of uranium enrichment by the gas centri.pdf:application/pdf},
}

@article{rothwell_market_2009,
	title = {Market {Power} in {Uranium} {Enrichment}},
	volume = {17},
	issn = {0892-9882},
	url = {https://doi.org/10.1080/08929880903423586},
	doi = {10.1080/08929880903423586},
	abstract = {Four firms dominate the international uranium enrichment market. Simultaneously, the nations that host enrichment facilities strongly discourage other nations from developing enrichment capacity, given its potential use in nuclear weapons production. Therefore, these four firms benefit from the exercise of national power to prevent entry into this market. This paper shows that these firms also benefit from increasing returns to scale. In similar national situations, this industry would be regulated or nationalized. This is because free markets do not necessarily lead to a socially optimal long-run equilibrium where the industry is necessarily concentrated, such that there is no proliferating entry, but is sufficiently diverse, so that no one national group can dictate prices, contract terms, or non-proliferation policy. Therefore, some form of international regulation might be necessary to discourage enrichment technology proliferation and assure enrichment supply at reasonable prices.},
	number = {2-3},
	urldate = {2022-03-27},
	journal = {Science \& Global Security},
	author = {ROTHWELL, GEOFFREY},
	month = oct,
	year = {2009},
	pages = {132--154},
	annote = {Publisher: Routledge \_eprint: https://doi.org/10.1080/08929880903423586},
	file = {Full Text:C\:\\Users\\abachmann\\Zotero\\storage\\U73YD8M8\\ROTHWELL - 2009 - Market Power in Uranium Enrichment.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\2QS84ZSB\\08929880903423586.html:text/html},
}

@book{villani_uranium_1979,
	series = {Topics in applied physics; v. 35},
	title = {Uranium enrichment},
	isbn = {0-387-09385-0},
	url = {https://www.osti.gov/biblio/5449407},
	abstract = {Uranium isotope separation science, technology in the field of industrial applications, and laboratory investigations of uranium isotope separation are treated in this book. Basic concepts for the mathematical treatment of the cascade separation processes and an original presentation of ideal nonsymmetric cascades are treated in the chapter entitled, Cascade theory. The chapter entitled, Gaseous diffusion, discusses this process which is the main industrial process for uranium enrichment today as well as an in depth treatment of the gas flow through the porous barrier and the relevant separation effects. The chapter on the centrifugation process covers essentially the conceptual and theoretical aspects of the process. An overall description of the separation nozzle process including both the physical principle and the technical aspects are discussed. The last two chapters in the book are devoted to new methods of uranium separation which are still in the laboratory stage. The laser method in which separation is obtained through selective photoexcitation of uranium atoms or molecules is treated in one chapter, and the other chapter deals with separation experiments with rotating plasmas and some advanced concepts like using ion cyclotron resonance effects to achieve isotope separation. (BLM)},
	language = {English},
	urldate = {2022-03-27},
	publisher = {Springer-Verlag,New York, NY},
	author = {Villani, S.},
	month = jan,
	year = {1979},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\ZW4665AQ\\5449407.html:text/html},
}

@misc{regalbuto_addressing_2020,
	title = {Addressing {HALEU} {Demand}},
	url = {https://inldigitallibrary.inl.gov/sites/sti/sti/Sort_24470.pdf},
	urldate = {2022-03-23},
	author = {Regalbuto, Monica C.},
	month = apr,
	year = {2020},
	file = {Sort_24470.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\YBAEMC26\\Sort_24470.pdf:application/pdf},
}

@misc{herczeg_high-assay_2019,
	title = {High-{Assay} {Low} {Enriched} {Uranium} ({HALEU})},
	url = {https://www.energy.gov/sites/prod/files/2019/04/f61/HALEU%20Report%20to%20NEAC%20Committee%203-28-19%20%28FINAL%29.pdf},
	author = {Herczeg, John W.},
	month = mar,
	year = {2019},
	file = {HALEU Report to NEAC Committee 3-28-19 (FINAL).pdf:C\:\\Users\\abachmann\\Zotero\\storage\\49QF7CDZ\\HALEU Report to NEAC Committee 3-28-19 (FINAL).pdf:application/pdf},
}

@techreport{crawford_fuel_2019,
	title = {Fuel {Fabrication} {Facility} {Study} for {FCF} {HALEU}},
	url = {https://www.osti.gov/biblio/1504421},
	abstract = {Nuclear energy technology developers seek to bring to market new advanced reactor designs and new light water reactor fuel designs, many of which would deploy fuel made from uranium with 235U enrichment ranging from 5\% to 19.75\%. There is currently no commercial supply of uranium in this enrichment range, which is higher than used in today’s light water reactors but still lower than the safeguards limit of 20\% 235U. This limitation is a barrier to development of demonstration of these new nuclear energy technologies. As a means to address this near-term need, DOE and Idaho National Laboratory (INL) has considered how the HALEU product from sodium-bonded spent fuel treatment in the INL Fuel Conditioning Facility (FCF), located at the Materials and Fuels Complex (MFC), might be provided and fabricated into some of the new fuel designs. The evaluation presented in this report addresses the potential establishment of two types of fuel fabrication capability at INL, represented generically as a ceramic-type (or pellet-type) fuel fabrication line and a metallic fuel fabrication line. Because the FCF HALEU feedstock contains residual transuranic contamination and a relatively small amount of residual fission products, fabrication with that material is necessarily performed inside of engineered confinement barriers, such as gloveboxes, which would be filled with inert gas for most of the fuel types considered. The throughput rate of the fabrication lines envisioned is 2.5 metric tons of HALEU fuel per year, which is judged to be sufficiently representative of engineering-scale. Space in three existing buildings was identified for consideration in this study of pre-conceptual equipment layouts. The scope and nature of the work needed to prepare each of the three buildings for each type of fuel fabrication was identified (though not in engineering detail), and three-dimensional models of envisioned fabrication equipment were laid out in each of the buildings to assess adequacy of space. The study concluded that either type of fuel fabrication line can feasibly be installed and operated in either of the three buildings. However, each of the three buildings presents different challenges in preparation, due to accommodating current missions that would need to be relocated or necessary decontamination and decommissioning work to free-up space for fuel fabrication, or due to complications of accessibility. Rough order-of-magnitude (ROM) cost estimates for preparing buildings begin at \$10M ( 20\%/+50\%) and would increase with increased complexity of building modifications. The cost of fabrication equipment and gloveboxes is roughly estimated to be \$21M (-20\%/+50\%) for a metallic fuel fabrication line and \$27M (-20\%/+50\%) for a ceramic/intermetallic fuel fabrication line. Nominal operating costs are estimated to be \$7M per year (in 2019 dollars), increasing from lower amounts needed as the operating crew is being assembled and trained.},
	language = {English},
	number = {INL/EXT-19-52614-Rev000},
	urldate = {2022-03-14},
	institution = {Idaho National Lab. (INL), Idaho Falls, ID (United States)},
	author = {Crawford, Doug C. and Baily, C. E. and Clark, C. R. and Fielding, R. S. and Marschman, S. C.},
	month = mar,
	year = {2019},
	doi = {10.2172/1504421},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\MEUBJAZQ\\JE9AE2KE.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\9VU6465K\\1504421.html:text/html},
}

@techreport{dixon_estimated_2022,
	title = {Estimated {HALEU} {Requirements} for {Advanced} {Reactors} to {Support} a {Net}-{Zero} {Emissions} {Economy} by 2050},
	url = {https://www.osti.gov/servlets/purl/1838156/},
	language = {en},
	number = {INL/EXT-21-64913-Rev000, 1838156},
	urldate = {2022-03-14},
	author = {Dixon, Brent and Kim, Son and Feng, Bo and Kim, Taek and Richards, Scott and Bae, Jin},
	month = jan,
	year = {2022},
	doi = {10.2172/1838156},
	pages = {INL/EXT--21--64913--Rev000, 1838156},
	file = {Dixon et al. - 2022 - Estimated HALEU Requirements for Advanced Reactors.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\UKNKKW5J\\8XC8PYRH.pdf:application/pdf},
}

@article{demkowicz_coated_2019,
	title = {Coated particle fuel: {Historical} perspectives and current progress},
	volume = {515},
	issn = {0022-3115},
	shorttitle = {Coated particle fuel},
	url = {https://www.sciencedirect.com/science/article/pii/S0022311518310213},
	doi = {10.1016/j.jnucmat.2018.09.044},
	abstract = {Coated particle fuel concepts date back some 60 years, and have evolved significantly from the relatively primitive pyrocarbon-coated kernels envisioned by the first pioneers. Improvements in particle design, coating layer properties, and kernel composition have produced the modern tristructural isotropic (TRISO) particle, capable of low statistical coating failure fractions and good fission product retention under extremely severe conditions, including temperatures of 1600 °C for hundreds of hours. The fuel constitutes one of the key enabling technologies for high-temperature gas-cooled reactors, allowing coolant outlet temperatures approaching 1000 °C and contributing to enhanced reactor safety due to the hardiness of the particles. TRISO fuel development has taken place in a number of countries worldwide, and several fuel qualification programs are currently in progress. In this paper, we discuss the unique history of particle fuel development and some key technology advances, concluding with some of the latest progress in UO2 and UCO TRISO fuel qualification.},
	language = {en},
	urldate = {2022-03-10},
	journal = {Journal of Nuclear Materials},
	author = {Demkowicz, Paul A. and Liu, Bing and Hunn, John D.},
	month = mar,
	year = {2019},
	keywords = {Coated particle fuel, High temperature gas cooled reactor, HTGR, TRISO, Tristructural isotropic},
	pages = {434--450},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\S3I53K74\\ZJTUCMWS.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\45RRUUJZ\\S0022311518310213.html:text/html},
}

@article{shiozawa_overview_2004,
	series = {Japan's {HTTR}},
	title = {Overview of {HTTR} design features},
	volume = {233},
	issn = {0029-5493},
	url = {https://www.sciencedirect.com/science/article/pii/S0029549304002341},
	doi = {10.1016/j.nucengdes.2004.07.016},
	abstract = {The Japan Atomic Energy Research Institute (JAERI) designed and constructed the high temperature engineering test reactor (HTTR) in order to establish and upgrade the technology basis for the high temperature gas-cooled reactor (HTGR) and develop the technology for high temperature heat applications. The HTTR is a helium-cooled and graphite-moderated HTGR with a thermal power of 30MW and a maximum reactor outlet coolant temperature of 950°C. The first criticality was attained on November 10, 1998 and the rated power operation with the reactor outlet coolant temperature of 850°C was achieved on December 7, 2001. Since 2002, safety demonstration tests simulating anticipated operational occurrences such as decrease of primary coolant flow-rate and reactivity insertion have been carried out to ensure safety during off-normal conditions. From 2005, various irradiation tests for fuels and materials will start. In addition, a hydrogen production test facility will be coupled with the HTTR by 2015 to produce hydrogen by nuclear. The history and future plan, major design features and R\&D programs of the HTTR are summarized in this paper.},
	language = {en},
	number = {1},
	urldate = {2022-03-10},
	journal = {Nuclear Engineering and Design},
	author = {Shiozawa, S. and Fujikawa, S. and Iyoku, T. and Kunitomi, K. and Tachibana, Y.},
	month = oct,
	year = {2004},
	pages = {11--21},
	file = {main.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\BZYQ4NT8\\main.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\ZHAZKA2Q\\S0029549304002341.html:text/html},
}

@article{powers_review_2010,
	title = {A review of {TRISO} fuel performance models},
	volume = {405},
	issn = {0022-3115},
	url = {https://www.sciencedirect.com/science/article/pii/S0022311510003284},
	doi = {10.1016/j.jnucmat.2010.07.030},
	abstract = {Several advanced reactor designs incorporate tristructural isotropic (TRISO) fuel particles to achieve high coolant temperature and high fuel burnup levels and thus require reliable and robust fuel performance models (FPMs) to evaluate reactor performance. This manuscript provides a detailed and concise review of the numerous published TRISO FPMs. The article begins with a brief review of TRISO fuel particles, before describing the important fuel behavior and failure mechanisms of TRISO fuel. Suggested material property correlations for use in TRISO fuel performance modeling are summarized with an emphasis on the limits of validity for those correlations and notes regarding their use and origin. A review of the major historical and current TRISO FPMs assesses each model’s capabilities and origin and provides a systematic comparison of the codes to document similarities and differences in their features. Finally, areas of improvement and unsolved problems are discussed that may limit the accuracy of TRISO fuel performance modeling.},
	language = {en},
	number = {1},
	urldate = {2022-03-10},
	journal = {Journal of Nuclear Materials},
	author = {Powers, Jeffrey J. and Wirth, Brian D.},
	month = oct,
	year = {2010},
	pages = {74--82},
	file = {Powers and Wirth - 2010 - A review of TRISO fuel performance models.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\BJHLY7NF\\CVRSFK6C.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\J33YKBGA\\S0022311510003284.html:text/html},
}

@inproceedings{venneri_fully_2011,
	address = {Hollywood, FL},
	title = {Fully {Ceramic} {Microencapsulated} {Fuels}: {A} {Transformational} {Technology} for {Present} and {Next} {Generation} {Reactors} - {Preliminary} analysis of {FCM} fuel reactor operation},
	volume = {104},
	url = {https://epubs.ans.org/?a=12071&_ga=2.107688578.1679227796.1646919142-287406757.1598467895},
	urldate = {2022-03-10},
	booktitle = {Transactions of the {American} {Nuclear} {Soceity} {Annual} {Meeting}},
	author = {Venneri, Francesco and Kim, Y. and Snead, L. L. and Terrani, K A and Ougouag, A and Tulenko, J E and Forsberg, C W and Peterson, P. F. and Lahoda, E. J.},
	month = jun,
	year = {2011},
	pages = {671--674},
	file = {ANS / Digital Nuclear Library / Transactions / Volume 104 / Number 1 / Pages 671-674:C\:\\Users\\abachmann\\Zotero\\storage\\FM2KEELN\\epubs.ans.org.html:text/html;Venneri et al. - 2011 - Fully Ceramic Microencapsulated Fuels A Transform.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\ZNW27EM5\\9B7V2GHS.pdf:application/pdf},
}

@phdthesis{passerini_sensitivity_2012,
	type = {{PhD} {Thesis}},
	title = {Sensitivity {Analysis} and {Optimization} of the {Nuclear} {Fuel} {Cycle}: {A} {Systematic} {Approach}},
	shorttitle = {Sensitivity {Analysis} and {Optimization} of the {Nuclear} {Fuel} {Cycle}},
	url = {https://ui.adsabs.harvard.edu/abs/2012PhDT.......216P},
	abstract = {For decades, nuclear energy development was based on the expectation that recycling of the fissionable materials in the used fuel from today's light water reactors into advanced (fast) reactors would be implemented as soon as technically feasible in order to extend the nuclear fuel resources. More recently, arguments have been made for deployment of fast reactors in order to reduce the amount of higher actinides, hence the longevity of radioactivity, in the materials destined to a geologic repository. The cost of the fast reactors, together with concerns about the proliferation of the technology of extraction of plutonium from used LWR fuel as well as the large investments in construction of reprocessing facilities have been the basis for arguments to defer the introduction of recycling technologies in many countries including the US. In this thesis, the impacts of alternative reactor technologies on the fuel cycle are assessed. Additionally, metrics to characterize the fuel cycles and systematic approaches to using them to optimize the fuel cycle are presented. The fuel cycle options of the 2010 MIT fuel cycle study are re-examined in light of the expected slower rate of growth in nuclear energy today, using the CAFCA (Code for Advanced Fuel Cycle Analysis). The Once Through Cycle (OTC) is considered as the base-line case, while advanced technologies with fuel recycling characterize the alternative fuel cycle options available in the future. The options include limited recycling in L WRs and full recycling in fast reactors and in high conversion LWRs. Fast reactor technologies studied include both oxide and metal fueled reactors. Additional fuel cycle scenarios presented for the first time in this work assume the deployment of innovative recycling reactor technologies such as the Reduced Moderation Boiling Water Reactors and Uranium-235 initiated Fast Reactors. A sensitivity study focused on system and technology parameters of interest has been conducted to test the robustness of the conclusions presented in the MIT Fuel Cycle Study. These conclusions are found to still hold, even when considering alternative technologies and different sets of simulation assumptions. Additionally, a first of a kind optimization scheme for the nuclear fuel cycle analysis is proposed and the applications of such an optimization are discussed. Optimization metrics of interest for different stakeholders in the fuel cycle (economics, fuel resource utilization, high level waste, transuranics/proliferation management, and environmental impact) are utilized for two different optimization techniques: a linear one and a stochastic one. Stakeholder elicitation provided sets of relative weights for the identified metrics appropriate to each stakeholder group, which were then successfully used to arrive at optimum fuel cycle configurations for recycling technologies. The stochastic optimization tool, based on a genetic algorithm, was used to identify non-inferior solutions according to Pareto's dominance approach to optimization. The main tradeoff for fuel cycle optimization was found to be between economics and most of the other identified metrics. (Copies available exclusively from MIT Libraries, libraries.mit.edu/docs - docs mit.edu)},
	urldate = {2022-03-10},
	author = {Passerini, Stefano},
	month = jan,
	year = {2012},
	keywords = {Engineering, Nuclear},
	annote = {Publication Title: Ph.D. Thesis ADS Bibcode: 2012PhDT.......216P},
	file = {Passerini - 2012 - Sensitivity Analysis and Optimization of the Nucle.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\R46VBLXL\\Passerini - 2012 - Sensitivity Analysis and Optimization of the Nucle.pdf:application/pdf},
}

@article{mckay_comparison_2000,
	title = {A {Comparison} of {Three} {Methods} for {Selecting} {Values} of {Input} {Variables} in the {Analysis} of {Output} {From} a {Computer} {Code}},
	volume = {42},
	issn = {0040-1706},
	doi = {10.1080/00401706.2000.10485979},
	abstract = {Two types of sampling plans are examined as alternatives to simple random sampling in Monte Carlo studies. These plans are shown to be improvements over simple random sampling with respect to variance for a class of estimators which includes the sample mean and the empirical distribution function.},
	number = {1},
	urldate = {2022-03-10},
	journal = {Technometrics},
	author = {McKay, M. D. and Beckman, R. J. and Conover, W. J.},
	month = feb,
	year = {2000},
	note = {Published:  https://www.tandfonline.com/doi/abs/10.1080/00401706.2000.10485979},
	keywords = {Variance reduction, Latin hypercube sampling, Sampling techniques, Simulation techniques},
	pages = {55--61},
	annote = {Publisher: Taylor \& Francis \_eprint: https://www.tandfonline.com/doi/pdf/10.1080/00401706.2000.10485979},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\T8EXKJ83\\Mckay et al. - 2000 - A Comparison of Three Methods for Selecting Values.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\WNQF64BA\\00401706.2000.html:text/html},
}

@techreport{passerini_sensitivity_2012-1,
	title = {Sensitivity analysis and optimization of the nuclear fuel cycle},
	url = {https://www.osti.gov/biblio/22107877},
	abstract = {A sensitivity study has been conducted to assess the robustness of the conclusions presented in the MIT Fuel Cycle Study. The Once Through Cycle (OTC) is considered as the base-line case, while advanced technologies with fuel recycling characterize the alternative fuel cycles. The options include limited recycling in LWRs and full recycling in fast reactors and in high conversion LWRs. Fast reactor technologies studied include both oxide and metal fueled reactors. The analysis allowed optimization of the fast reactor conversion ratio with respect to desired fuel cycle performance characteristics. The following parameters were found to significantly affect the performance of recycling technologies and their penetration over time: Capacity Factors of the fuel cycle facilities, Spent Fuel Cooling Time, Thermal Reprocessing Introduction Date, and in core and Out-of-core TRU Inventory Requirements for recycling technology. An optimization scheme of the nuclear fuel cycle is proposed. Optimization criteria and metrics of interest for different stakeholders in the fuel cycle (economics, waste management, environmental impact, etc.) are utilized for two different optimization techniques (linear and stochastic). Preliminary results covering single and multi-variable and single and multi-objective optimization demonstrate the viability of the optimization scheme. (authors)},
	language = {English},
	urldate = {2022-03-10},
	institution = {American Nuclear Society - ANS; La Grange Park (United States)},
	author = {Passerini, S. and Kazimi, M. S. and Shwageraus, E.},
	month = jul,
	year = {2012},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\725VXN9U\\22107877.html:text/html},
}

@techreport{busquim_e_silva_system_2008,
	type = {Technical {Report}},
	title = {A {System} {Dynamics} {Study} of the {Nuclear} {Fuel} {Cycle} with {Recycling}: {Options} and {Outcomes} for the {US} and {Brazil}},
	shorttitle = {A {System} {Dynamics} {Study} of the {Nuclear} {Fuel} {Cycle} with {Recycling}},
	abstract = {A system dynamics simulation technique is applied to generate a new version of the CAFCA code to study mass flows in the nuclear fuel cycle, and the impact of different options for advanced reactors and fuel recycling facilities on the inventory and distribution of transuranics (TRU). Several nuclear fuel cycle options are studied for U.S. and Brazil markets, and special consideration is given to potential collaboration between the two countries. This includes the impact of advanced nuclear technologies, under a prescribed growth in demand for nuclear electricity, on demand for uranium resources, uranium enrichment, and fuel reprocessing facilities, and on total cost of nuclear electricity over the next few decades. Introduction of fuel recycling reduces the growing demand for uranium, and the long-term need for storage of radioactive spent fuel. However, the timing of introduction of recycling is important for proper technology development, and the rate of deployment is restrained by the industrial capacity as well as the desire for high utilization factor of the deployed facilities over their life time, and that is reflected in the assessments. The nuclear fuel cycle is modeled as a high level structure diagram, which provides an overview of the interconnections among its blocks without showing all details, and as a structure-policy diagram which details the decision rules applied to the structure. The high level structure diagram represents the nuclear fuel cycle; the fleet of thermal and fast reactors; the separation and reprocessing plants; the waste repository; the spent fuel storage; and the paths for the fuel and waste mass transfer. In addition, an economic model is added to study different cases under the same assumptions. The economic model is based on the forecasted need for advanced reactors and recycling facilities, assuming that all costs are recovered within the nuclear energy system. Different recycling technology options are included in the code: (1) Thermal recycling in LWRs using Combined Non-Fertile and UO2 Fuel (CONFU), (2) Recycling of TRU in fertile-free fast cores of Actinide Burner Reactors (ABR); and (3) Fast recycling of TRU with UO[subscript 2] in self-sustaining Gas-cooled Fast Reactors (GFR). Case studies for different advanced technology introduction dates and for distinct TRU depletion rates are examined. In particular, the code is 3 equipped to simulate the introduction of two recycling technology options with a prescribed allocation of the TRU supply between them. The simulation results show that early introduction of the GFR recycling scheme leads to the most significant reduction in uranium consumption and enrichment requirements, thus delaying the eventual depletion date of uranium ore. The GFR requires less uranium resources due to the use of TRU as recycled fuel and near unity fissile conversion ratio. However, in a nonbreeding reactor system, the consumption of U continues to grow, and the TRU needed to start fast reactors will be growing at a constrained rate. On the other hand, the CONFU recycling scheme keeps the TRU inventory in the entire system well below other schemes, and guarantees equilibrium between the generation and consumption of transuranics without investments in fast reactors. CONFU incinerates more TRU than the GFR and ABR schemes during the simulation period. Also, it reduces the TRU sent to the repository for disposal by orders of magnitude. The ABR scheme does the same but requires the introduction of fast reactors. Nevertheless, the CONFU and ABR schemes have no significant impact on the amount of uranium resources consumption or enrichment requirements. Economic analysis indicates that the CONFU technology is more attractive at current uranium prices, and that fast recycling becomes as attractive as thermal recycling at higher uranium prices. The results also show that if a nuclear fuel cycle state/reactor state collaboration with Brazil is started, there will be a significant impact on the U.S. cumulative TRU inventory at interim storage, enrichment requirements, uranium consumption, and number of advanced fuel facilities. The results show that a nuclear partnership without the introduction of advanced nuclear technologies would not have advantages for the U.S. Furthermore, a nuclear collaboration allows a higher ratio of fast reactors to total installed nuclear electric capacity in the U.S.},
	language = {en},
	urldate = {2022-03-10},
	institution = {Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program},
	author = {Busquim e Silva, R. and Kazimi, Mujid S. and Hejzlar, Pavel},
	month = nov,
	year = {2008},
	note = {Published:  https://dspace.mit.edu/handle/1721.1/75238},
	annote = {Accepted: 2012-12-05T19:36:16Z},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\DGS7SVDP\\75238.html:text/html},
}

@techreport{piet_assessment_2011,
	title = {Assessment of {Tools} and {Data} for {System}-{Level} {Dynamic} {Analyses}},
	abstract = {The only fuel cycle for which dynamic analyses and assessments are not needed is the null fuel cycle - no nuclear power. For every other concept, dynamic analyses are needed and can influence relative desirability of options. Dynamic analyses show how a fuel cycle might work during transitions from today's partial fuel cycle to something more complete, impact of technology deployments, location of choke points, the key time lags, when benefits can manifest, and how well parts of fuel cycles work together. This report summarizes the readiness of existing Fuel Cycle Technology (FCT) tools and data for conducting dynamic analyses on the range of options. VISION is the primary dynamic analysis tool. Not only does it model mass flows, as do other dynamic system analysis models, but it allows users to explore various potential constraints. The only fuel cycle for which constraints are not important are those in concept advocates PowerPoint presentations; in contrast, comparative analyses of fuel cycles must address what constraints exist and how they could impact performance. The most immediate tool need is extending VISION to the thorium/U233 fuel cycle. Depending on further clarification of waste management strategies in general and for specific fuel cycle candidates, waste management sub-models in VISION may need enhancement, e.g., more on 'co-flows' of non-fuel materials, constraints in waste streams, or automatic classification of waste streams on the basis of user-specified rules. VISION originally had an economic sub-model. The economic calculations were deemed unnecessary in later versions so it was retired. Eventually, the program will need to restore and improve the economics sub-model of VISION to at least the cash flow stage and possibly to incorporating cost constraints and feedbacks. There are multiple sources of data that dynamic analyses can draw on. In this report, 'data' means experimental data, data from more detailed theoretical or empirical calculations on technology performance, and assumptions such as the earliest date a technology can be deployed. The only fuel cycles for which we currently have adequate data are those we are sure we will never build, e.g., a PUREX plant in the U.S. For actual candidates, even for once through LWRs, there remain missing data such as how the fuel cycle would be completed with a geologic repository. The most immediate data needs are probably basic reactor physics data for new concepts and data associated with waste management for anything other than current technology. The readiness of tools and data is fluid and depends on what purposes are envisioned to drive upcoming analyses and further definition of the waste-related characteristics of fuel cycle candidates. Tools and data sets evolve as needs evolve. Thus, much of the document explains that if the FCT program wants a certain type of analysis, then the tools and data needs are as indicated. For example, functions can be treated as either commodities or facilities. Reactors, separation, fuel fabrication, repository are treated as facility types. Other functions such as uranium mining, conversion, enrichment, and waste packaging and non-repository disposal are treated as commodities and therefore not modeled as extensively. In summary, the tools are functional and can answer many fuel cycle questions but some analyses will require that the tools be modified to support those analyses.},
	language = {English},
	number = {INL/EXT-11-22588},
	urldate = {2022-03-10},
	institution = {Idaho National Lab. (INL), Idaho Falls, ID (United States)},
	author = {Piet, Steven J. and Soelberg, Nick R.},
	month = jun,
	year = {2011},
	doi = {10.2172/1031709},
	note = {Published:  https://www.osti.gov/biblio/1031709},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\BGP3NPRB\\Piet and Soelberg - 2011 - Assessment of Tools and Data for System-Level Dyna.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\BVKRG6L9\\1031709.html:text/html},
}

@article{kim_nuclear_2015,
	title = {Nuclear fuel cycle cost estimation and sensitivity analysis of unit costs on the basis of an equilibrium model},
	volume = {47},
	issn = {1738-5733},
	url = {https://www.sciencedirect.com/science/article/pii/S1738573315000224},
	doi = {10.1016/j.net.2014.12.018},
	abstract = {This paper examines the difference in the value of the nuclear fuel cycle cost calculated by the deterministic and probabilistic methods on the basis of an equilibrium model. Calculating using the deterministic method, the direct disposal cost and Pyro-SFR (sodium-cooled fast reactor) nuclear fuel cycle cost, including the reactor cost, were found to be 66.41 mills/kWh and 77.82 mills/kWh, respectively (1 mill = one thousand of a dollar, i.e., 10−3 \$). This is because the cost of SFR is considerably expensive. Calculating again using the probabilistic method, however, the direct disposal cost and Pyro-SFR nuclear fuel cycle cost, excluding the reactor cost, were found be 7.47 mills/kWh and 6.40 mills/kWh, respectively, on the basis of the most likely value. This is because the nuclear fuel cycle cost is significantly affected by the standard deviation and the mean of the unit cost that includes uncertainty. Thus, it is judged that not only the deterministic method, but also the probabilistic method, would also be necessary to evaluate the nuclear fuel cycle cost. By analyzing the sensitivity of the unit cost in each phase of the nuclear fuel cycle, it was found that the uranium unit price is the most influential factor in determining nuclear fuel cycle costs.},
	language = {en},
	number = {3},
	urldate = {2022-03-10},
	journal = {Nuclear Engineering and Technology},
	author = {Kim, S. K. and Ko, W. I. and Youn, S. R. and Gao, R. X.},
	month = apr,
	year = {2015},
	keywords = {Uncertainty, Deterministic method, Direct disposal, Equilibrium model, Nuclear fuel cycle cost, Probabilistic method, Pyro-SFR fuel cycle, Pyroprocess, Unit cost},
	pages = {306--314},
}

@inproceedings{brinton_nuclear_2013-1,
	address = {Atlanta, GA},
	title = {Nuclear {Fuel} {Cycle} {Analysis} and {Optimization} with the {Code} for {Advanced} {Fuel} {Cycles} {Assessment} ({CASCA})},
	volume = {108},
	booktitle = {Transactions of the {American} {Nuclear} {Soceity} {Annual} {Meeting}},
	author = {Brinton, Samuel and Passerini, Stefano and Kazimi, Mujid},
	month = jun,
	year = {2013},
	pages = {131--133},
	file = {Brinton et al. - 2013 - Nuclear Fuel Cycle Analysis and Optimization with .pdf:C\:\\Users\\abachmann\\Zotero\\storage\\ESYDMAED\\Brinton et al. - 2013 - Nuclear Fuel Cycle Analysis and Optimization with .pdf:application/pdf},
}

@article{chadwick_endfb-vii1_2011,
	series = {Special {Issue} on {ENDF}/{B}-{VII}.1 {Library}},
	title = {{ENDF}/{B}-{VII}.1 {Nuclear} {Data} for {Science} and {Technology}: {Cross} {Sections}, {Covariances}, {Fission} {Product} {Yields} and {Decay} {Data}},
	volume = {112},
	issn = {0090-3752},
	shorttitle = {{ENDF}/{B}-{VII}.1 {Nuclear} {Data} for {Science} and {Technology}},
	url = {https://www.sciencedirect.com/science/article/pii/S009037521100113X},
	doi = {10.1016/j.nds.2011.11.002},
	abstract = {The ENDF/B-VII.1 library is our latest recommended evaluated nuclear data file for use in nuclear science and technology applications, and incorporates advances made in the five years since the release of ENDF/B-VII.0. These advances focus on neutron cross sections, covariances, fission product yields and decay data, and represent work by the US Cross Section Evaluation Working Group (CSEWG) in nuclear data evaluation that utilizes developments in nuclear theory, modeling, simulation, and experiment. The principal advances in the new library are: (1) An increase in the breadth of neutron reaction cross section coverage, extending from 393 nuclides to 423 nuclides; (2) Covariance uncertainty data for 190 of the most important nuclides, as documented in companion papers in this edition; (3) R-matrix analyses of neutron reactions on light nuclei, including isotopes of He, Li, and Be; (4) Resonance parameter analyses at lower energies and statistical high energy reactions for isotopes of Cl, K, Ti, V, Mn, Cr, Ni, Zr and W; (5) Modifications to thermal neutron reactions on fission products (isotopes of Mo, Tc, Rh, Ag, Cs, Nd, Sm, Eu) and neutron absorber materials (Cd, Gd); (6) Improved minor actinide evaluations for isotopes of U, Np, Pu, and Am (we are not making changes to the major actinides 235,238U and 239Pu at this point, except for delayed neutron data and covariances, and instead we intend to update them after a further period of research in experiment and theory), and our adoption of JENDL-4.0 evaluations for isotopes of Cm, Bk, Cf, Es, Fm, and some other minor actinides; (7) Fission energy release evaluations; (8) Fission product yield advances for fission-spectrum neutrons and 14 MeV neutrons incident on 239Pu; and (9) A new decay data sublibrary. Integral validation testing of the ENDF/B-VII.1 library is provided for a variety of quantities: For nuclear criticality, the VII.1 library maintains the generally-good performance seen for VII.0 for a wide range of MCNP simulations of criticality benchmarks, with improved performance coming from new structural material evaluations, especially for Ti, Mn, Cr, Zr and W. For Be we see some improvements although the fast assembly data appear to be mutually inconsistent. Actinide cross section updates are also assessed through comparisons of fission and capture reaction rate measurements in critical assemblies and fast reactors, and improvements are evident. Maxwellian-averaged capture cross sections at 30 keV are also provided for astrophysics applications. We describe the cross section evaluations that have been updated for ENDF/B-VII.1 and the measured data and calculations that motivated the changes, and therefore this paper augments the ENDF/B-VII.0 publication [M. B. Chadwick, P. Obložinský, M. Herman, N. M. Greene, R. D. McKnight, D. L. Smith, P. G. Young, R. E. MacFarlane, G. M. Hale, S. C. Frankle, A. C. Kahler, T. Kawano, R. C. Little, D. G. Madland, P. Moller, R. D. Mosteller, P. R. Page, P. Talou, H. Trellue, M. C. White, W. B. Wilson, R. Arcilla, C. L. Dunford, S. F. Mughabghab, B. Pritychenko, D. Rochman, A. A. Sonzogni, C. R. Lubitz, T. H. Trumbull, J. P. Weinman, D. A. Br, D. E. Cullen, D. P. Heinrichs, D. P. McNabb, H. Derrien, M. E. Dunn, N. M. Larson, L. C. Leal, A. D. Carlson, R. C. Block, J. B. Briggs, E. T. Cheng, H. C. Huria, M. L. Zerkle, K. S. Kozier, A. Courcelle, V. Pronyaev, and S. C. van der Marck, “ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology,” Nuclear Data Sheets 107, 2931 (2006)].},
	language = {en},
	number = {12},
	urldate = {2022-11-01},
	journal = {Nuclear Data Sheets},
	author = {Chadwick, M. B. and Herman, M. and Obložinský, P. and Dunn, M. E. and Danon, Y. and Kahler, A. C. and Smith, D. L. and Pritychenko, B. and Arbanas, G. and Arcilla, R. and Brewer, R. and Brown, D. A. and Capote, R. and Carlson, A. D. and Cho, Y. S. and Derrien, H. and Guber, K. and Hale, G. M. and Hoblit, S. and Holloway, S. and Johnson, T. D. and Kawano, T. and Kiedrowski, B. C. and Kim, H. and Kunieda, S. and Larson, N. M. and Leal, L. and Lestone, J. P. and Little, R. C. and McCutchan, E. A. and MacFarlane, R. E. and MacInnes, M. and Mattoon, C. M. and McKnight, R. D. and Mughabghab, S. F. and Nobre, G. P. A. and Palmiotti, G. and Palumbo, A. and Pigni, M. T. and Pronyaev, V. G. and Sayer, R. O. and Sonzogni, A. A. and Summers, N. C. and Talou, P. and Thompson, I. J. and Trkov, A. and Vogt, R. L. and van der Marck, S. C. and Wallner, A. and White, M. C. and Wiarda, D. and Young, P. G.},
	month = dec,
	year = {2011},
	pages = {2887--2996},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\X4GNF6HS\\Chadwick et al. - 2011 - ENDFB-VII.1 Nuclear Data for Science and Technolo.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\5X4QCCJW\\S009037521100113X.html:text/html},
}

@article{kiegiel_management_2022,
	title = {Management of {Radioactive} {Waste} from {HTGR} {Reactors} including {Spent} {TRISO} {Fuel}—{State} of the {Art}},
	volume = {15},
	copyright = {http://creativecommons.org/licenses/by/3.0/},
	issn = {1996-1073},
	url = {https://www.mdpi.com/1996-1073/15/3/1099},
	doi = {10.3390/en15031099},
	abstract = {In light of the increasing demand for energy sources in the world and the need to meet climate goals set by countries, there is growing global interest in high temperature gas cooled reactors (HTGRs), especially as they are known to be inherently safe nuclear reactors. The safety of HTGRs results, among other, from the nature of the nuclear fuel used in them in the form of coated TRISO particles (tri-structural-isotropic) and the reduction of the total amount of radioactive waste generated. This paper reviews numerous methods used to ensure the sustainable, feasible management and long-term storage of HTGR nuclear waste for the protection of the environment and society. The types of waste generated in the HTGR cycle are presented as well as the methods of their characterization, which are important for long-time storage and final disposal. Two leading nuclear fuel cycle strategies, the once-through cycle (direct disposal or open cycle) and the twice-through cycle (recycling or partially closed cycle), are discussed also in relation to TRISO spent fuel. A short review of the possibilities of treatment of TRISO spent nuclear fuel from HTGR reactors is made.},
	language = {en},
	number = {3},
	urldate = {2022-10-28},
	journal = {Energies},
	author = {Kiegiel, Katarzyna and Herdzik-Koniecko, Irena and Fuks, Leon and Zakrzewska-Kołtuniewicz, Grażyna},
	month = jan,
	year = {2022},
	keywords = {reprocessing, disposal, TRISO spent fuel},
	pages = {1099},
	file = {Kiegiel et al. - 2022 - Management of Radioactive Waste from HTGR Reactors including Spent TRISO Fuel—State of the Art.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\PBU52HES\\Kiegiel et al. - 2022 - Management of Radioactive Waste from HTGR Reactors including Spent TRISO Fuel—State of the Art.pdf:application/pdf},
}

@mastersthesis{richter_isotopic_2022-1,
	address = {Urbana, IL},
	title = {{ISOTOPIC} {AND} {REACTOR} {PHYSICS} {CHARACTERIZATION} {OF} {A} {GAS}-{COOLED}, {PEBBLE}-{BED} {MICROREACTOR}},
	language = {en},
	school = {University of Illinois at Urbana-Champaign},
	author = {Richter, Zoë},
	month = may,
	year = {2022},
	file = {Richter - ISOTOPIC AND REACTOR PHYSICS CHARACTERIZATION OF A.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\R9VDP2FJ\\Richter - ISOTOPIC AND REACTOR PHYSICS CHARACTERIZATION OF A.pdf:application/pdf},
}

@article{suparlina_burnup_2019,
	title = {Burnup {Calculation} {Study} of {Pebble} {Bed} {Equilibrium} {Core}},
	volume = {1198},
	issn = {1742-6596},
	url = {https://doi.org/10.1088/1742-6596/1198/2/022036},
	doi = {10.1088/1742-6596/1198/2/022036},
	abstract = {Reaktor Daya Eksperimental (RDE) is a high temperature gas-cooled reactor (HTGR) producing a 10 MW thermal with a pebble bed fuels which being developed by BATAN. The purpose of this paper is to study the burnup distribution and characteristic in the equilibrium core for different multipass recirculation method. Understanding the reactor physics, in particular the burnup, is important for optimum design and safety analysis of nuclear reactor. Related with the design approval phase of RDE, this study provides a design data which needed for the RDE’s safety analysis report, e.g. fuel pebble performance analysis. Analysis in this study was performed using PEBBED diffusion code. PEBBED is designed to solve the neutronics and thermalhydraulics parameter cases for high temperature pebble bed reactors for different fuel recirculation including once-through-then-out (OTTO) and multipass scheme. The reactor core calculation was performed by applying multipass scheme with variation from 5 passes up to 15 passes. With energy and power as inputs, the calculations produce the burnup fraction at the end of the cycle and the fast and thermal neutron fluxes in 8 energy groups. The calculation results showed that the lowest 5 passes fuel recirculation pattern has the highest and lowest minimum discharged burnup value. This is related to the average power distribution in the core which means more passes will flatter the burnup distribution including the power distribution and also seen in the value of flux and power peaking factor produced. power peaking factor produced.},
	language = {en},
	number = {2},
	urldate = {2022-10-03},
	journal = {Journal of Physics: Conference Series},
	author = {Suparlina, L. and Setiadipura, T. and {Suwoto}},
	month = apr,
	year = {2019},
	note = {Publisher: IOP Publishing},
	pages = {022036},
	file = {IOP Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\YIHDZ78F\\Suparlina et al. - 2019 - Burnup Calculation Study of Pebble Bed Equilibrium.pdf:application/pdf},
}

@article{acir_criticality_2011,
	title = {Criticality and burnup analyses of a {PBMR}-400 full core using {Monte} {Carlo} calculation method},
	volume = {38},
	issn = {03064549},
	url = {https://linkinghub.elsevier.com/retrieve/pii/S0306454910003828},
	doi = {10.1016/j.anucene.2010.10.013},
	abstract = {In this study, the criticality and burnup analyses have been performed for full core model of Pebble Bed Modular Reactors, such as PBMR-400, using the computer codes MCNP5.1.4 and MONTEBURNS 2.0. Three different pebble distributions, namely; Body Centered Cubic (BCC) (packing fraction = 68\%), Random Packing (RP) (packing fraction = 61\%) and Simple Cubic (SC) (packing fraction = 52\%) were selected for the analyses. The calculated core effective multiplication factor, keff, for BCC, RP and SC came to be 1.2395, 1.2357 and 1.2223, respectively. The core life for these distributions were calculated as  1200, 1000, and 800 Effective Full Power Days (EFPDs), whereas, the corresponding burnups came out to be  99,000,  92,000 and  86,000 MWD/T, respectively, for end of life keff set equal to 1.02.},
	language = {en},
	number = {2-3},
	urldate = {2022-09-30},
	journal = {Annals of Nuclear Energy},
	author = {Acır, Adem and Coşkun, Hasan and Şahin, Hacı Mehmet and Erol, Özgür},
	month = feb,
	year = {2011},
	pages = {298--301},
	file = {Acır et al. - 2011 - Criticality and burnup analyses of a PBMR-400 full.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\KC8Y5NRF\\Acır et al. - 2011 - Criticality and burnup analyses of a PBMR-400 full.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\6VSNMD2F\\S0306454910003828.html:text/html},
}

@misc{korsnick_updated_2021,
	title = {Updated {Need} for {High}-{Assay} {Low} {Enriched} {Uranium}},
	url = {https://www.nei.org/CorporateSite/media/filefolder/resources/letters-filings-comments/NEI-Letter-for-Secretary-Granholm_HALEU-2021.pdf},
	urldate = {2022-03-14},
	author = {Korsnick, Maria},
	month = dec,
	year = {2021},
	file = {NEI-Letter-for-Secretary-Granholm_HALEU-2021.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\X979SKBR\\NEI-Letter-for-Secretary-Granholm_HALEU-2021.pdf:application/pdf},
}

@misc{korsnick_updated_2020,
	title = {Updated {Need} for {High}-{Assay} {Low} {Enriched} {Uranium}},
	url = {https://www.nei.org/resources/letters-filings-comments/updated-need-for-haleu},
	language = {eng},
	author = {Korsnick, Maria},
	month = jul,
	year = {2020},
	file = {NEI-Letter-to-the-Secretary-of-Energy-HALEU-Update.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\2F5LLTI7\\NEI-Letter-to-the-Secretary-of-Energy-HALEU-Update.pdf:application/pdf},
}

@misc{korsnick_need_2018,
	title = {Need for {High}-{Assay} {Low} {Enriched} {Uranium}},
	url = {https://www.nei.org/resources/letters-filings-comments/nei-letter-perry-need-haleu},
	language = {eng},
	author = {Korsnick, Maria},
	month = jul,
	year = {2018},
	file = {letter-perry-haleu-20180705.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\7BZYIMAG\\6K84NMMB.pdf:application/pdf},
}

@inproceedings{bagdatlioglu_characterizing_2016,
	title = {Characterizing the {United} {States} {Nuclear} {Used} {Fuel} {Inventory} {Using} the {Cyclus} {Fuel} {Cycle} {Simulator}},
	url = {https://memagazineselect.asmedigitalcollection.asme.org/ICONE/proceedings/ICONE24/50015/V001T02A027/251456},
	doi = {10.1115/ICONE24-61031},
	language = {en},
	urldate = {2022-09-26},
	publisher = {American Society of Mechanical Engineers Digital Collection},
	author = {Bagdatlioglu, Cem and Flanagan, Robert and Schneider, Erich},
	month = oct,
	year = {2016},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\KFHDU8Y9\\251456.html:text/html},
}

@misc{flanagan_xsgen_2017,
	title = {{XSgen}: {A} {Cross} {Section} {Generation} {Methodology} for {Fuel} {Cycle} {Simulation}},
	shorttitle = {{XSgen}},
	url = {http://arxiv.org/abs/1712.02241},
	doi = {10.48550/arXiv.1712.02241},
	abstract = {This work investigates a method for generating medium fidelity reactor model cross sections. The methodology used here couples a neutron transport code with a depletion calculator. Together the two can be used to generate time dependent group cross sections for medium fidelity reactor models in fuel cycle simulation. This work analyzes XSgen, a software that performs the functions mentioned above. Addtionally, it is shown that XSgen is capable of creating datasets for a medium fidelity reactor model known as Bright-lite. The results of this work show that XSgen produces datasets that match NEA benchmarks for both uranium based LWR, and MOX reactors.},
	urldate = {2022-09-26},
	publisher = {arXiv},
	author = {Flanagan, Robert and Scopatz, Anthony},
	month = dec,
	year = {2017},
	note = {arXiv:1712.02241 [nucl-th]},
	keywords = {Nuclear Theory},
	annote = {Comment: Preprint},
	file = {arXiv Fulltext PDF:C\:\\Users\\abachmann\\Zotero\\storage\\E6MMJU5R\\Flanagan and Scopatz - 2017 - XSgen A Cross Section Generation Methodology for .pdf:application/pdf;arXiv.org Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\SVJZLW7L\\1712.html:text/html},
}

@techreport{skutnik_origen-based_2017-1,
	title = {{ORIGEN}-based {Nuclear} {Fuel} {Inventory} {Module} for {Fuel} {Cycle} {Assessment}: {Final} {Project} {Report}},
	shorttitle = {{ORIGEN}-based {Nuclear} {Fuel} {Inventory} {Module} for {Fuel} {Cycle} {Assessment}},
	url = {https://www.osti.gov/biblio/1364128},
	abstract = {The goal of this project, “ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment" is to create a physics-based reactor depletion and decay module for the Cyclus nuclear fuel cycle simulator in order to assess nuclear fuel inventories over a broad space of reactor operating conditions. The overall goal of this approach is to facilitate evaluations of nuclear fuel inventories for a broad space of scenarios, including extended used nuclear fuel storage and cascading impacts on fuel cycle options such as actinide recovery in used nuclear fuel, particularly for multiple recycle scenarios. The advantages of a physics-based approach (compared to a recipe-based approach which has been typically employed for fuel cycle simulators) is in its inherent flexibility; such an approach can more readily accommodate the broad space of potential isotopic vectors that may be encountered under advanced fuel cycle options. In order to develop this flexible reactor analysis capability, we are leveraging the Origen nuclear fuel depletion and decay module from SCALE to produce a standalone “depletion engine” which will serve as the kernel of a Cyclus-based reactor analysis module. The ORIGEN depletion module is a rigorously benchmarked and extensively validated tool for nuclear fuel analysis and thus its incorporation into the Cyclus framework can bring these capabilities to bear on the problem of evaluating long-term impacts of fuel cycle option choices on relevant metrics of interest, including materials inventories and availability (for multiple recycle scenarios), long-term waste management and repository impacts, etc. Developing this Origen-based analysis capability for Cyclus requires the refinement of the Origen analysis sequence to the point where it can reasonably be compiled as a standalone sequence outside of SCALE; i.e., wherein all of the computational aspects of Origen (including reactor cross-section library processing and interpolation, input and output processing, and depletion/decay solvers) can be self-contained into a single executable sequence. Further, to embed this capability into other software environments (such as the Cyclus fuel cycle simulator) requires that Origen’s capabilities be encapsulated into a portable, self-contained library which other codes can then call directly through function calls, thereby directly accessing the solver and data processing capabilities of Origen. Additional components relevant to this work include modernization of the reactor data libraries used by Origen for conducting nuclear fuel depletion calculations. This work has included the development of new fuel assembly lattices not previously available (such as for CANDU heavy-water reactor assemblies) as well as validation of updated lattices for light-water reactors updated to employ modern nuclear data evaluations. The CyBORG reactor analysis module as-developed under this workscope is fully capable of dynamic calculation of depleted fuel compositions from all commercial U.S. reactor assembly types as well as a number of international fuel types, including MOX, VVER, MAGNOX, and PHWR CANDU fuel assemblies. In addition, the Origen-based depletion engine allows for CyBORG to evaluate novel fuel assembly and reactor design types via creation of Origen reactor data libraries via SCALE. The establishment of this new modeling capability affords fuel cycle modelers a substantially improved ability to model dynamically-changing fuel cycle and reactor conditions, including recycled fuel compositions from fuel cycle scenarios involving material recycle into thermal-spectrum systems.},
	language = {English},
	number = {DOE/NEUP-13-5415},
	urldate = {2022-09-26},
	institution = {Univ. of Tennessee, Knoxville, TN (United States)},
	author = {Skutnik, Steven E.},
	month = jun,
	year = {2017},
	doi = {10.2172/1364128},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\ESCTCZHA\\Skutnik - 2017 - ORIGEN-based Nuclear Fuel Inventory Module for Fue.pdf:application/pdf;Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\XY82R49E\\1364128.html:text/html},
}

@article{ernoult_automated_2021,
	title = {Automated selection of nuclides and reactions of interest in a depletion simulation. {Precision} loss estimation for multiple outputs},
	volume = {135},
	issn = {0149-1970},
	url = {https://www.sciencedirect.com/science/article/pii/S0149197021000688},
	doi = {10.1016/j.pnucene.2021.103702},
	abstract = {To accelerate depletion calculations, it is common to only consider a selection of isotopes. Simulating only a limited number of nuclides leads inevitably to some bias on the outputs of the depletion simulation. Most methods used are either implicit or dedicated to specific cases. This paper presents a new method, based on physics consideration and an explicit algorithm, that automatically selects isotopes and reactions for a depletion calculation. This method uses the creation and simplification of a nucleus tree gathering and linking together all nuclides that can possibly be created during the depletion process. This is performed by recursively adding nuclides possibly created from nuclides previously in the tree through decay or nuclear reaction. After the creation of the tree, it can be simplified by automatically cutting nuclides and reaction out through 3 processes: half-life threshold, cross-section threshold and reaction type cut. Using these simplification processes, the presented method leads to important calculation cost reduction (up to 40\%) with effect on outputs lower than 3 times their stochastic standard deviation.},
	language = {en},
	urldate = {2022-09-26},
	journal = {Progress in Nuclear Energy},
	author = {Ernoult, Marc and Liang, Jiali and Doligez, Xavier and Thiollière, Nicolas and Meplan, Olivier and Bouneau, Sandra and David, Sylvain},
	month = may,
	year = {2021},
	keywords = {Fuel cycle, Depletion, Approximation, Isotopes selection},
	pages = {103702},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\66C4QQ4U\\Ernoult et al. - 2021 - Automated selection of nuclides and reactions of i.pdf:application/pdf},
}

@patent{venneri_fully_2016,
	title = {Fully ceramic nuclear fuel and related methods},
	url = {https://patents.google.com/patent/US9299464B2/en},
	nationality = {US},
	language = {en},
	assignee = {LOGOS TECHNOLOGIES LLC, UT Battelle LLC},
	number = {US9299464B2},
	urldate = {2022-09-16},
	author = {Venneri, Francesco and Katoh, Yutai and SNEAD, Lance Lewis},
	month = mar,
	year = {2016},
	keywords = {fuel, isotropic, nuclear, silicon carbide, tristructural},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\9S37JLWL\\Venneri et al. - 2016 - Fully ceramic nuclear fuel and related methods.pdf:application/pdf},
}

@incollection{kramer_genetic_2017,
	address = {Cham},
	series = {Studies in {Computational} {Intelligence}},
	title = {Genetic {Algorithms}},
	isbn = {978-3-319-52156-5},
	url = {https://doi.org/10.1007/978-3-319-52156-5_2},
	abstract = {Genetic Algorithms are heuristic search approaches that are applicable to a wide range of optimization problems. This flexibility makes them attractive for many optimization problems in practice. Evolution is the basis of Genetic Algorithms. The current variety and success of species is a good reason for believing in the power of evolution. Species are able to adapt to their environment. They have developed to complex structures that allow the survival in different kinds of environments. Mating and getting offspring to evolve belong to the main principles of the success of evolution. These are good reasons for adapting evolutionary principles to solving optimization problems.},
	language = {en},
	urldate = {2022-12-13},
	booktitle = {Genetic {Algorithm} {Essentials}},
	publisher = {Springer International Publishing},
	author = {Kramer, Oliver},
	editor = {Kramer, Oliver},
	year = {2017},
	doi = {10.1007/978-3-319-52156-5_2},
	keywords = {Crossover Operator, Fitness Function, Genetic Algorithm, Mutation Operator, Solution Space},
	pages = {11--19},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\RMQEWILV\\Kramer - 2017 - Genetic Algorithms.pdf:application/pdf},
}

@phdthesis{chee_fluoride-salt-cooled_2022,
	address = {Urbana, IL},
	type = {Dissertation},
	title = {Fluoride-{Salt}-{Cooled} {High} {Temperature} {Reactor} {Design} {Optimization} with {Evolutionary} {Algorithms}},
	copyright = {Copyright 2021 Gwendolyn Jin Yi Chee},
	url = {https://github.com/arfc/2022-chee-dissertation},
	abstract = {Additive manufacturing of reactor core components removes the geometric constraints required by conventional manufacturing, such as slabs as fuel planks and cylinders as fuel rods. Due to the expansion of the potential design space facilitated through additive manufacturing, reactor designers need to find methods, such as generative design, to explore the design space efficiently. In this defense, I will show that I successfully applied evolutionary algorithms to conduct generative reactor design optimization for a fluoride-salt-cooled high-temperature reactor (FHR). I achieved this through three distinct research efforts: 1) furthering our understanding of the FHR design’s complexities through neutronics and temperature modeling, 2) creating an open-source tool that enables generative design reactor optimization with evolutionary algorithms, and 3) applying the tool to the FHR to optimize for non-conventional geometries and fuel distributions},
	school = {University of Illinois at Urbana-Champaign},
	author = {Chee, Gwendolyn Jin Yi},
	month = aug,
	year = {2022},
	file = {2022-chee-dissertation-pres.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\Y93FYTHR\\2022-chee-dissertation-pres.pdf:application/pdf;Chee - 2021 - Fluoride-Salt-Cooled High Temperature Reactor Desi.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\EXF7M46A\\Chee - 2021 - Fluoride-Salt-Cooled High Temperature Reactor Desi.pdf:application/pdf},
}

@inproceedings{bachmann_sensitivity_2022,
	address = {Phoenix, AZ},
	title = {Sensitivity analysis of fuel cycle transitions using {Cyclus}-{Dakota}},
	booktitle = {Proceedings of the {International} {High} {Level} {Radioactive} {Waste} {Management} {Conference}},
	author = {Bachmann, Amanda M. and Richards, Scott and Munk, Madicken and Feng, Bo},
	month = nov,
	year = {2022},
}

@article{mceligot_thermal_nodate,
	title = {Thermal {Properties} of {G}-348 {Graphite}},
	language = {en},
	author = {McEligot, Donald M and Swank, W David and Cottle, David L and Valentin, Francisco I},
	pages = {23},
	file = {McEligot et al. - Thermal Properties of G-348 Graphite.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\FIKSULLC\\McEligot et al. - Thermal Properties of G-348 Graphite.pdf:application/pdf},
}

@article{petersen_properties_nodate,
	title = {The {Properties} of {Helium}: {Density}, {Specific} {Heats}, {Viscosity}, and {Thermal} {Conductivity} at {Pressures} from 1 to 100 bar and from {Room} {Temperature} to about 1800 {K}},
	abstract = {An estimation of the properties of helium is carried out on the basis of a literature survey. The ranges of pressure and temperature chosen are applicable to helium-cooled atomic reactor design. A brief outline of vhe theory for the properties is incorporated, and comparisons of the recommended data with the data calculated from intermolecular potential functions are presented.},
	language = {en},
	author = {Petersen, Helge},
	pages = {46},
	file = {Petersen - The Properties of Helium Density, Specific Heats,.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\2LIV6RDR\\Petersen - The Properties of Helium Density, Specific Heats,.pdf:application/pdf},
}

@article{fink_thermophysical_2000,
	title = {Thermophysical properties of uranium dioxide},
	volume = {279},
	issn = {0022-3115},
	url = {https://www.sciencedirect.com/science/article/pii/S0022311599002731},
	doi = {10.1016/S0022-3115(99)00273-1},
	abstract = {Experimental data on thermodynamic and transport properties of solid and liquid UO2 have been reviewed and analyzed to obtain consistent equations for the thermophysical properties. Thermodynamic properties that have been assessed include enthalpy, heat capacity, enthalpy of fusion, thermal expansion, density, surface tension and vapor pressure. Transport properties that have been assessed are thermal diffusivity, thermal conductivity, viscosity, emissivity and optical constants. The assessments include a review of the experiments and data, review of previous recommendations, analysis of data to obtain new recommendations, determination of uncertainties in the recommended values, and comparisons of new recommendations with data and previous recommendations.},
	language = {en},
	number = {1},
	urldate = {2022-11-08},
	journal = {Journal of Nuclear Materials},
	author = {Fink, J. K.},
	month = mar,
	year = {2000},
	pages = {1--18},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\XKPNXFAC\\Fink - 2000 - Thermophysical properties of uranium dioxide.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\QHTDHCNB\\S0022311599002731.html:text/html},
}

@article{johnson_serpenttools_2020,
	title = {{serpentTools}: {A} {Python} {Package} for {Expediting} {Analysis} with {Serpent}},
	volume = {194},
	issn = {0029-5639},
	shorttitle = {{serpentTools}},
	url = {https://doi.org/10.1080/00295639.2020.1723992},
	doi = {10.1080/00295639.2020.1723992},
	abstract = {The serpentTools Python package is presented as a useful and efficient alternative for processing Serpent results. One positive attribute of Serpent is that many output files are exported directly in a MATLAB format, allowing for results to be loaded with minimal to no effort. However, some files for larger analyses may require immense amounts of memory to load and store all the data, leading to long wait times. To expedite the process of data handling and ease common analyses, the Computational Reactor Engineering lab at the Georgia Institute of Technology has released and is maintaining the serpentTools Python package: a set of data parsers and containers intended to streamline analysis with Serpent outputs. The parsers are capable of processing large outputs with ease, and yield all data to the user in a simple object-oriented framework. Data can be read into Python in comparable or better times than MATLAB, with the option to store only data needed for a specific purpose. Furthermore, common analyses are implemented directly into the package to expedite frequent analysis, including plotting meshed data and flux specta. serpentTools is designed to be a useful and practical manner by which the Serpent community can load and analyze data inside a Python environment. This paper presents the Python package, highlighting some basic features, and compares capabilities to similar platforms.},
	number = {11},
	urldate = {2022-11-04},
	journal = {Nuclear Science and Engineering},
	author = {Johnson, Andrew E. and Kotlyar, Dan and Terlizzi, Stefano and Ridley, Gavin},
	month = nov,
	year = {2020},
	note = {Publisher: Taylor \& Francis
\_eprint: https://doi.org/10.1080/00295639.2020.1723992},
	keywords = {Serpent, Python, open source, visualization},
	pages = {1016--1024},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\PGSSI29M\\Johnson et al. - 2020 - serpentTools A Python Package for Expediting Anal.pdf:application/pdf},
}

@misc{venneri_micro_2019,
	address = {Warsaw, Poland},
	title = {Micro {Modular} {Reactor} ({MMR}) {Energy} {Systems}},
	url = {https://www.ifnec.org/ifnec/upload/docs/application/pdf/2019-09/3-4._usnc_mmr.pdf},
	urldate = {2022-11-01},
	author = {Venneri, Francesco},
	month = sep,
	year = {2019},
	file = {3-4._usnc_mmr.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\VVIGHVI6\\3-4._usnc_mmr.pdf:application/pdf},
}

@misc{noauthor_nuclear_nodate,
	title = {Nuclear {Data} for {Safeguards}},
	url = {https://www-nds.iaea.org/sgnucdat/a6.htm},
	urldate = {2023-03-31},
	file = {Nuclear Data for Safeguards:C\:\\Users\\abachmann\\Zotero\\storage\\37ESM6EG\\a6.html:text/html},
}

@article{birkett_recent_2005,
	title = {Recent {Developments} in the {Purex} {Process} for {Nuclear} {Fuel} {Reprocessing}: {Complexant} {Based} {Stripping} for {Uranium}/{Plutonium} {Separation}},
	volume = {59},
	copyright = {Copyright (c) 2005 Swiss Chemical Society},
	issn = {2673-2424},
	shorttitle = {Recent {Developments} in the {Purex} {Process} for {Nuclear} {Fuel} {Reprocessing}},
	url = {https://www.chimia.ch/chimia/article/view/2005_898},
	doi = {10.2533/000942905777675327},
	abstract = {In order to recycle potentially valuable uranium and plutonium, the Purex process has been successfully used to reprocess spent nuclear fuel for several decades now at industrial scales. The process has developed over this period to treat higher burnup fuels, oxide as well as metal
 fuels within fewer solvent extraction cycles with reduced waste arisings. Within the context of advanced fuel cycle scenarios, there has been renewed international interest recently in separation technologies for recovering actinides from spent fuel. Aqueous fuel processing research and development
 has included further enhancement of the Purex process as well as the development of minor actinide partitioning technologies that use new extractants. The use of single cycle Purex solvent extraction flowsheets and centrifugal contactors are key objectives in the development of such advanced
 Purex processes in future closed fuel cycles. These advances lead to intensified processes, reducing the costs of plants and the volumes of wastes arising. By adopting other flowsheet changes, such as reduced fission product decontamination factors, U/Pu co-processing and Pu/Np co-stripping,
 further improvements can be made addressing issues such as proliferation resistance and minor actinide burning, without adverse effects on the products. One interesting development is the demonstration that simple hydroxamic acid complexants can very effectively separate U from Np and Pu in
 such advanced Purex flowsheets.},
	language = {en},
	number = {12},
	urldate = {2023-03-29},
	journal = {CHIMIA},
	author = {Birkett, J. Eddie and Carrott, Michael J. and Fox, O. Danny and Jones, Chris J. and Maher, Chris J. and Roube, Cécile V. and Taylor, Robin J. and Woodhead, David A.},
	month = dec,
	year = {2005},
	note = {Number: 12},
	keywords = {Actinides, Acetohydroxamic acid, Centrifugal contactors, Nuclear fuel reprocessing, Purex process},
	pages = {898--898},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\BN6ZIEDG\\Birkett et al. - 2005 - Recent Developments in the Purex Process for Nucle.pdf:application/pdf},
}

@book{nash_advanced_2011,
	title = {Advanced {Separation} {Techniques} for {Nuclear} {Fuel} {Reprocessing} and {Radioactive} {Waste} {Treatment}},
	isbn = {978-0-85709-227-4},
	abstract = {Advanced separations technology is key to closing the nuclear fuel cycle and relieving future generations from the burden of radioactive waste produced by the nuclear power industry. Nuclear fuel reprocessing techniques not only allow for recycling of useful fuel components for further power generation, but by also separating out the actinides, lanthanides and other fission products produced by the nuclear reaction, the residual radioactive waste can be minimised. Indeed, the future of the industry relies on the advancement of separation and transmutation technology to ensure environmental protection, criticality-safety and non-proliferation (i.e., security) of radioactive materials by reducing their long-term radiological hazard.Advanced separation techniques for nuclear fuel reprocessing and radioactive waste treatment provides a comprehensive and timely reference on nuclear fuel reprocessing and radioactive waste treatment. Part one covers the fundamental chemistry, engineering and safety of radioactive materials separations processes in the nuclear fuel cycle, including coverage of advanced aqueous separations engineering, as well as on-line monitoring for process control and safeguards technology. Part two critically reviews the development and application of separation and extraction processes for nuclear fuel reprocessing and radioactive waste treatment. The section includes discussions of advanced PUREX processes, the UREX+ concept, fission product separations, and combined systems for simultaneous radionuclide extraction. Part three details emerging and innovative treatment techniques, initially reviewing pyrochemical processes and engineering, highly selective compounds for solvent extraction, and developments in partitioning and transmutation processes that aim to close the nuclear fuel cycle. The book concludes with other advanced techniques such as solid phase extraction, supercritical fluid and ionic liquid extraction, and biological treatment processes.With its distinguished international team of contributors, Advanced separation techniques for nuclear fuel reprocessing and radioactive waste treatment is a standard reference for all nuclear waste management and nuclear safety professionals, radiochemists, academics and researchers in this field.A comprehensive and timely reference on nuclear fuel reprocessing and radioactive waste treatmentDetails emerging and innovative treatment techniques, reviewing pyrochemical processes and engineering, as well as highly selective compounds for solvent extractionDiscusses the development and application of separation and extraction processes for nuclear fuel reprocessing and radioactive waste treatment},
	language = {en},
	publisher = {Elsevier},
	author = {Nash, Kenneth L. and Lumetta, Gregg J.},
	month = mar,
	year = {2011},
	note = {Google-Books-ID: z4xwAgAAQBAJ},
	keywords = {Technology \& Engineering / Environmental / Waste Management, Technology \& Engineering / Power Resources / Nuclear, Business \& Economics / Industries / Energy},
}

@article{chang_depletion_2000,
	title = {Depletion {Analysis} of {Mixed}-{Oxide} {Fuel} {Pins} in {Light} {Water} {Reactors} and the {Advanced} {Test} {Reactor}},
	volume = {129},
	issn = {0029-5450},
	url = {https://doi.org/10.13182/NT00-A3065},
	doi = {10.13182/NT00-A3065},
	abstract = {An experiment containing weapons-grade mixed-oxide (WG-MOX) fuel has been designed and is being irradiated in the Advanced Test Reactor (ATR) at the Idaho National Engineering and Environmental Laboratory (INEEL). The ability to accurately predict fuel pin performance is an essential requirement for the MOX fuel test assembly design. Detailed radial fission power and temperature profile effects and fission gas release in the fuel pin are a function of the fuel pin’s temperature, fission power, and fission product and actinide concentration profiles. In addition, the burnup-dependent profile analyses in irradiated fuel pins is important for fuel performance analysis to support the potential licensing of the MOX fuel made from WG-plutonium and depleted uranium for use in U.S. reactors.The MCNP Coupling With ORIGEN2 burnup calculation code (MCWO) can analyze the detailed burnup profiles of WG-MOX and reactor-grade mixed-oxide (RG-MOX) fuel pins. The validated code MCWO can provide the best-estimate neutronic characteristics of fuel burnup performance analysis. Applying this capability with a new minicell method allows calculation of detailed nuclide concentration and power distributions within the MOX pins as a function of burnup. This methodology was applied to MOX fuel in a commercial pressurized water reactor and in an experiment currently being irradiated in the ATR. The prediction of nuclide concentration profiles and power distributions in irradiated MOX pins via this new methodology can provide insights into MOX fuel performance.},
	number = {3},
	urldate = {2023-03-28},
	journal = {Nuclear Technology},
	author = {Chang, Gray S. and Ryskamp, John M.},
	month = mar,
	year = {2000},
	note = {Publisher: Taylor \& Francis
\_eprint: https://doi.org/10.13182/NT00-A3065},
	pages = {326--337},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\RE8ILKMU\\Chang and Ryskamp - 2000 - Depletion Analysis of Mixed-Oxide Fuel Pins in Lig.pdf:application/pdf},
}

@misc{noauthor_optimization_2023,
	title = {Optimization with constraints · snl-dakota · {Discussion} \#29},
	url = {https://github.com/orgs/snl-dakota/discussions/29},
	abstract = {I am using the soga method for optimization of a problem with a linear constraint, x+y+z=100. I see in the User\&\#39;s Manual that this method can handle this constraint form directly and in the Ref...},
	language = {en},
	urldate = {2023-03-20},
	journal = {GitHub},
	month = mar,
	year = {2023},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\NV29JYRY\\29.html:text/html},
}

@misc{noauthor_dakota_2021,
	title = {Dakota {Reference} {Manual}: moga},
	url = {https://dakota.sandia.gov//sites/default/files/docs/6.15/html-ref/method-moga.html},
	urldate = {2023-02-27},
	month = nov,
	year = {2021},
	file = {Dakota Reference Manual\: moga:C\:\\Users\\abachmann\\Zotero\\storage\\H5EGT3DN\\method-moga.html:text/html},
}

@article{angelova_tuning_2011,
	title = {Tuning {Genetic} {Algorithm} {Parameters} to {Improve} {Convergence} {Time}},
	volume = {2011},
	issn = {1687-806X},
	url = {https://www.hindawi.com/journals/ijce/2011/646917/},
	doi = {10.1155/2011/646917},
	abstract = {Fermentation processes by nature are complex, time-varying, and highly nonlinear. As dynamic systems their modeling and further high-quality control are a serious challenge. The conventional optimization methods cannot overcome the fermentation processes peculiarities and do not lead to a satisfying solution. As an alternative, genetic algorithms as a stochastic global optimization method can be applied. For the purpose of parameter identification of a fed-batch cultivation of S. cerevisiae altogether four kinds of simple and four kinds of multipopulation genetic algorithms have been considered. Each of them is characterized with a different sequence of implementation of main genetic operators, namely, selection, crossover, and mutation. The influence of the most important genetic algorithm parameters—generation gap, crossover, and mutation rates has—been investigated too. Among the considered genetic algorithm parameters, generation gap influences most significantly the algorithm convergence time, saving up to 40\% of time without affecting the model accuracy.},
	language = {en},
	urldate = {2023-03-10},
	journal = {International Journal of Chemical Engineering},
	author = {Angelova, Maria and Pencheva, Tania},
	month = sep,
	year = {2011},
	note = {Publisher: Hindawi},
	pages = {e646917},
	file = {Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\4N9NZALY\\Angelova and Pencheva - 2011 - Tuning Genetic Algorithm Parameters to Improve Con.pdf:application/pdf},
}

@misc{adams_dakota_2021,
	title = {Dakota, {A} {Multilevel} {Parallel} {Object}-{Oriented} {Framework} for {Design} {Optimization}, {Parameter} {Estimation}, {Uncertainty} {Quantification}, and {Sensitivity} {Analysis}: {Version} 6.15 {User}’s {Manual}},
	abstract = {The Dakota toolkit provides a flexible and extensible interface between simulation codes and iterative analysis
methods. Dakota contains algorithms for optimization with gradient and nongradient-based methods; uncertainty
quantification with sampling, reliability, and stochastic expansion methods; parameter estimation with nonlinear
least squares methods; and sensitivity/variance analysis with design of experiments and parameter study methods.
These capabilities may be used on their own or as components within advanced strategies such as surrogatebased
optimization, mixed integer nonlinear programming, or optimization under uncertainty. By employing
object-oriented design to implement abstractions of the key components required for iterative systems analyses,
the Dakota toolkit provides a flexible and extensible problem-solving environment for design and performance
analysis of computational models on high performance computers.
This report serves as a user’s manual for the Dakota software and provides capability overviews and procedures
for software execution, as well as a variety of example studies.
Dakota},
	publisher = {Sandia National Laboratories},
	author = {Adams, Brian M. and Eldred, Michael Scott and Geraci, Gianluca and Bohnhoff, William J.},
	month = nov,
	year = {2021},
	file = {Adams et al. - 2019 - Dakota, A Multilevel Parallel Object-Oriented Fram.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\PMXYEYHJ\\Adams et al. - 2019 - Dakota, A Multilevel Parallel Object-Oriented Fram.pdf:application/pdf},
}

@article{chiandussi_comparison_2012,
	title = {Comparison of multi-objective optimization methodologies for engineering applications},
	volume = {63},
	issn = {0898-1221},
	url = {https://www.sciencedirect.com/science/article/pii/S0898122111010406},
	doi = {10.1016/j.camwa.2011.11.057},
	abstract = {Computational models describing the behavior of complex physical systems are often used in the engineering design field to identify better or optimal solutions with respect to previously defined performance criteria. Multi-objective optimization problems arise and the set of optimal compromise solutions (Pareto front) has to be identified by an effective and complete search procedure in order to let the decision maker, the designer, to carry out the best choice. Four multi-objective optimization techniques are analyzed by describing their formulation, advantages and disadvantages. The effectiveness of the selected techniques for engineering design purposes is verified by comparing the results obtained by solving a few benchmarks and a real structural engineering problem concerning an engine bracket of a car.},
	language = {en},
	number = {5},
	urldate = {2023-02-27},
	journal = {Computers \& Mathematics with Applications},
	author = {Chiandussi, G. and Codegone, M. and Ferrero, S. and Varesio, F. E.},
	month = mar,
	year = {2012},
	keywords = {Finite element method, Multi-objective optimization, Method effectiveness, Pareto front, Structural engineering},
	pages = {912--942},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\C35EHPCH\\Chiandussi et al. - 2012 - Comparison of multi-objective optimization methodo.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\7NDUV2YJ\\S0898122111010406.html:text/html},
}

@inproceedings{skulborstad_multi-objective_2018,
	title = {Multi-{Objective} {Optimization} for {Coupled} {Mechanics}-{Dynamics} {Analyses} of {Composite} {Structures}},
	isbn = {978-1-60595-534-6},
	url = {http://www.dpi-proceedings.com/index.php/asc33/article/view/26122},
	doi = {10.12783/asc33/26122},
	language = {en},
	urldate = {2023-02-27},
	booktitle = {American {Society} for {Composites} 2018},
	publisher = {DEStech Publications, Inc.},
	author = {Skulborstad, Alyssa and Nelson, Stacy},
	month = nov,
	year = {2018},
	file = {Skulborstad and Nelson - 2018 - Multi-Objective Optimization for Coupled Mechanics.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\78M26R9Y\\Skulborstad and Nelson - 2018 - Multi-Objective Optimization for Coupled Mechanics.pdf:application/pdf},
}

@article{zitzler_tutorial_2004,
	title = {A tutorial on evolutionary multiobjective optimization},
	volume = {535},
	url = {https://www.eckartzitzler.ch/img/publications/zlb2003a.pdf},
	urldate = {2023-02-21},
	journal = {Metaheuristics for multiobjective optimisation},
	author = {Zitzler, Eckart and Laumanns, Marco and Bleuler, Stefan},
	year = {2004},
	pages = {21--40},
	file = {zlb2003a.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\YMWAAAIM\\zlb2003a.pdf:application/pdf},
}

@misc{noauthor_dakota_2021-1,
	title = {Dakota {Reference} {Manual}: linear\_constraints},
	url = {https://dakota.sandia.gov//sites/default/files/docs/6.14/html-ref/topic-linear_constraints.html},
	urldate = {2023-02-13},
	journal = {Dakota Reference Manual version 6.14},
	month = may,
	year = {2021},
	file = {Dakota Reference Manual\: linear_constraints:C\:\\Users\\abachmann\\Zotero\\storage\\IE7W4UAY\\topic-linear_constraints.html:text/html},
}

@techreport{nea_meeting_2022,
	address = {Paris},
	title = {Meeting {Climate} {Change} {Targets}: {The} {Role} of {Nuclear} {Energy}},
	shorttitle = {Meeting {Climate} {Change} {Targets}},
	url = {https://www.oecd-nea.org/jcms/pl_69396/meeting-climate-change-targets-the-role-of-nuclear-energy?details=true},
	abstract = {All credible models show that nuclear energy has an important role to play in global climate change mitigation efforts (e.g. IEA, 2021; BNEF, 2021; IIASA, 2021). Despite clear analyses from many sources, including the NEA, that point to the need for a massive, “all-the-above” approach that includes ...},
	language = {en},
	number = {NEA 7628},
	urldate = {2023-05-26},
	institution = {OECD Nuclear Energy Agency},
	author = {NEA},
	year = {2022},
	file = {Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\ZNJYAQ2G\\meeting-climate-change-targets-the-role-of-nuclear-energy.html:text/html},
}

@inproceedings{mulder_deep_2008,
	address = {Washington, DC, USA},
	title = {Deep {Burn} {Strategy} for {Pure} {Reactor}-{Grade} {Plutonium} in {Pebble} {Bed} {High} {Temperature} {Gas}-{Cooled} {Reactors}},
	isbn = {978-0-7918-4854-8 978-0-7918-3834-1},
	url = {https://asmedigitalcollection.asme.org/HTR/proceedings/HTR2008/48548/263/334899},
	doi = {10.1115/HTR2008-58082},
	abstract = {In this article an advanced fuel cycle for pebble bed reactors is introduced that can safely and efficiently incinerate pure reactor-grade Pu [Pu(LWR)], thereby fulfilling the bulk of the GNEP waste incineration requirements.},
	language = {en},
	urldate = {2023-05-10},
	booktitle = {Fourth {International} {Topical} {Meeting} on {High} {Temperature} {Reactor} {Technology}, {Volume} 1},
	publisher = {ASMEDC},
	author = {Mulder, Eben and Serfontein, Dawid and Teuchert, Eberhard},
	month = jan,
	year = {2008},
	pages = {263--278},
	file = {Mulder et al. - 2008 - Deep Burn Strategy for Pure Reactor-Grade Plutoniu.pdf:C\:\\Users\\abachmann\\Zotero\\storage\\83IERU25\\Mulder et al. - 2008 - Deep Burn Strategy for Pure Reactor-Grade Plutoniu.pdf:application/pdf},
}

@incollection{herbst_6_2011,
	series = {Woodhead {Publishing} {Series} in {Energy}},
	title = {6 - {Standard} and advanced separation: {PUREX} processes for nuclear fuel reprocessing},
	isbn = {978-1-84569-501-9},
	shorttitle = {6 - {Standard} and advanced separation},
	url = {https://www.sciencedirect.com/science/article/pii/B9781845695019500062},
	abstract = {The PUREX process for separating uranium and plutonium from irradiated nuclear fuels has been extensively studied and successfully operated industrially over the preceding five plus decades. It is anticipated that PUREX will play an important role in upcoming and advanced future nuclear fuel cycles. The first objective of this chapter is to provide the background information required to status the present state of the art as currently practiced at the industrial scale. The second objective is to examine the modifications ready, or nearly so, for implementation into the next generation of PUREX reprocessing facilities, thereby further expanding the utility and operation of the process for use in nuclear fuel cycles of the future.},
	language = {en},
	urldate = {2023-05-09},
	booktitle = {Advanced {Separation} {Techniques} for {Nuclear} {Fuel} {Reprocessing} and {Radioactive} {Waste} {Treatment}},
	publisher = {Woodhead Publishing},
	author = {Herbst, R. S. and Baron, P. and Nilsson, M.},
	editor = {Nash, Kenneth L. and Lumetta, Gregg J.},
	month = jan,
	year = {2011},
	doi = {10.1533/9780857092274.2.141},
	keywords = {nuclear fuel cycle, nuclear separations, plutonium separation, PUREX, solvent extraction, tributyl phosphate, uranium separation},
	pages = {141--175},
	file = {ScienceDirect Full Text PDF:C\:\\Users\\abachmann\\Zotero\\storage\\5QK5EN77\\Herbst et al. - 2011 - 6 - Standard and advanced separation PUREX proces.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\abachmann\\Zotero\\storage\\GH6MVMAV\\B9781845695019500062.html:text/html},
}

@inproceedings{baker_comparison_1963,
	address = {Argonne National Laboratory},
	title = {Comparison of the value of plutoinum and uranium isotopes in fast reactors},
	booktitle = {{PROCEEDINGS} {OF} {THE} {CONFERENCE} {ON} {BREEDING}, {ECONOMICS} {AND} {SAFETY} {IN} {LARGE} {FAST} {POWER} {REACTORS}},
	author = {Baker, A. R. and Ross, R. W.},
	month = oct,
	year = {1963},
}