msr-archive

curated documents pertaining to early molten salt reactor research.

poor text formatting in many of the publically available pdf scans of documents pertaining to early molten salt reactors make it cumbersome to sift out specific details. this repository is intending to make a searchable archive of ocr text files of documents pertaining to molten salt reactors, the need of which stem from the msre cad file project.

documents are rescanned with optical character recognition (ocr) using ocrmypdf, tesseract, and training set 'eng.traineddata'.

disclaimer: this repository is not intended to be a distribution of pdf documents, or an infringement on any possible copyright claims. for the original documents we refer to other sites, such as ornl's library catalog or energyfromthorium.

this repo uses git lfs (git large file storage) to manage version history of pdf's. so to clone this repo with the pdf's to your system you'll need to install git and git-lfs.

to search the repository for a keyword or phase it's recommended to use the atom editor's 'search in folder' function on the '/ocr' folder as is demonstrated here for the keyword 'msbr' using the plus and minus buttons at the top the context can be expanded or contracted. the individual pdf documents of interest in the '/docs' folder can then be opened with a pdf viewer. this method can be used to find documents with relevant information. be aware that the ocr is not great and there can be issues with missing spaces and wrong identification of letters and numbers, e.g. 'l00p' instead of 'loop'.

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index

• Nuclear Science and Engineering
• Fluid Fuel Reactors
  • Part I: Aqueous Homogeneous Reactors
  • Part II: Molten-Salt Reactors
  • Part III: Liquid Metal Fuel Reactors
• Nuclear Applications and Technology
  • volume 8
  • volume 10
• ORNL Reports Related to Liquid-Fluoride Reactors and Technology
• ORNL Technical Memoranda Related to the Molten-Salt Reactor Program
• ORNL Central Files Related to the Molten-Salt Reactor Program
• Liquid-Chloride Reactors
• EIP Documents
• Assorted Documents
• New Piles Commitee Documents

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Nuclear Science and Engineering, 2 2 (February 1957).

article	filename	ocr
Molten Fluorides as Power Reactor Fuels	NSE_moltenFluorides	txt
The Aircraft Reactor Experiment--Design and Construction	NSE_ARE_Design	txt
The Aircraft Reactor Experiment--Physics	NSE_ARE_Physics	txt
The Aircraft Reactor Experiment--Operation	SE_ARE_Operation	txt

---

Fluid Fuel Reactors, Addison-Wesley (1958).

part	filename	ocr
Part I: Aqueous Homogeneous Reactors	FFR_part1	txt
Part II: Molten-Salt Reactors	FFR_part2	txt
Part III: Liquid Metal Fuel Reactors	FFR_part3	txt

Part I: Aqueous Homogeneous Reactors

chapter	filename	ocr
Chapter 1: Homogeneous Reactors and their Development	FFR_chap01	txt
Chapter 2: Nuclear Characteristics of One- and Two-Region Homogeneous Reactors	FFR_chap02	txt
Chapter 3: Properties of Aqueous Fuel Solutions	FFR_chap03	txt
Chapter 4: Technology of Aqueous Suspensions	FFR_chap04	txt
Chapter 5: Integrity of Metals in Homogeneous Reactor Media	FFR_chap05	txt
Chapter 6: Chemical Processing	FFR_chap06	txt
Chapter 7: Design and Construction of Experimental Homogeneous Reactors	FFR_chap07	txt
Chapter 8: Component Development	FFR_chap08	txt
Chapter 9: Large-Scale Homogeneous Reactor Studies	FFR_chap09	txt
Chapter 10: Homogeneous Reactor Cost Studies	FFR_chap10	txt

Part II: Molten-Salt Reactors

chapter	filename	ocr
Chapter 11: Introduction	FFR_chap11	txt
Chapter 12: Chemical Aspects of Molten Fluoride Salt Reactor Fuels	FFR_chap12	txt
Chapter 13: Construction Materials for Molten-Salt Reactors	FFR_chap13	txt
Chapter 14: Nuclear Aspects of Molten-Salt Reactors	FFR_chap14	txt
Chapter 15: Equipment for Molten-Salt Reactors Heat-Transfer Systems	FFR_chap15	txt
Chapter 16: Aircraft Reactor Experiment	FFR_chap16	txt
Chapter 17: Conceptual Design of a Power Reactor	FFR_chap17	txt

Part III: Liquid Metal Fuel Reactors

chapter	filename	ocr
Chapter 18: Liquid Metal Fuel Reactors	FFR_chap18	txt
Chapter 19: Reactor Physics for Liquid Metal Reactors Design	FFR_chap19	txt
Chapter 20: Composition and Properties of Liquid Metal Fuels	FFR_chap20	txt
Chapter 21: Materials of Construction--Metallurgy	FFR_chap21	txt
Chapter 22: Chemical Processing	FFR_chap22	txt
Chapter 23: Engineering Design	FFR_chap23	txt
Chapter 24: Liquid-Metal Fuel Reactor Design Study	FFR_chap24	txt
Chapter 25: Additional Liquid Metal Reactors	FFR_chap06	txt

---

Nuclear Applications and Technology

volume 8 2 (February 1970).

article	filename	ocr
Preface: Molten Salt Reactors	NAT_preface	txt
Molten-Salt Reactors--History, Status, and Potential	NAT_MSRintro	txt
Experience with the Molten-Salt Reactor Experiment	NAT_MSREexperience	txt
Molten-Salt Reactor Chemistry	NAT_MSRchemistry	txt
New Developments in Materials for Molten-Salt Reactors	NAT_MSRmaterials	txt
Engineering Development of the MSBR Fuel Recycle	NAT_MSBRrecycle	txt
Graphite and Xenon Behavior and Their Influence on Molten-Salt Reactor Design	NAT_graphiteXenon	txt
The Design And Performance Features Of A Single-Fluid Molten-Salt Breeder Reactor	NAT_MSBRdesign	txt
Reactor Physics and Fuel Cycle Analyses	NAT_MSBRfuelcycle	txt

volume 10 2 (February 1971).

article	filename	ocr
Experiences with Dynamic Testing Methods at the MSRE	NAT_MSREdynamicsTesting	txt
Theoretical Dynamics Analysis of the MSRE	NAT_MSREdynamicsAnalysis	txt

---

ORNL Reports Related to Liquid-Fluoride Reactors and Technology

report	filename	date	ocr
Uses For Uranium-233: What Should Be Kept for Future Needs?	ORNL-6952	1999-09	txt
Interim Assessment of the Denatured 233U Fuel Cycle	ORNL-5388	1978-12	txt
Engineering Tests of the Metal Transfer Process from MSBR Fuel Salt	ORNL-5176	1977-02	txt
Mass Transfer Coefficients between LiF-BeF2-ThF4 and Bismuth	ORNL-5143	1976-11	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 29, 1976	ORNL-5132	1976-08	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1975	ORNL-5078	1976-02	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1975	ORNL-5047	1975-09	txt
Program Plan for the Development of Molten-Salt Breeder Reactors	ORNL-5018	1974-12	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1974	ORNL-5011	1975-06	txt
An Assessment of Industrial Energy Options Based on Coal and Nuclear Systems	ORNL-4995	1975-07	txt
Development and Construction of a Molybdenum Test Stand	ORNL-4874	1972-12	txt
Fission Product Behavior in the MSRE	ORNL-4865	1975-10	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1972	ORNL-4832	1973-03	txt
Development of the Variable-Gap Technique for Measuring the Thermal Conductivity of Fluoride Salt Mixtures	ORNL-4831	1973-02	txt
The ORNL Automated Orbital Pipe Welding Systems	ORNL-4830	1973-01	txt
Intergranular Cracking of INOR-8 in the MSRE	ORNL-4829	1972-11	txt
Development Status of Molten-Salt Breeder Reactors	ORNL-4812	1972-08	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 29, 1972	ORNL-4782	1972-10	txt
Considerations in the Long Term Management of High-Level Active Wastes	ORNL-4762	1972-02	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1971	ORNL-4728	1972-02	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1971	ORNL-4676	1971-08	txt
Reactivity Balance Calculations and Long-Term Reactivity Behavior with 235U in the MSRE	ORNL-4674	1972-02	txt
Chemical Aspects of MSRE Operations	ORNL-4658	1971-12	txt
ORIGEN - The ORNL Isotope Generation and Depletion Code	ORNL-4628	1973-05	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1970	ORNL-4622	1971-01	txt
Preparation and Handling of Salt Mixtures for the MSRE	ORNL-4616	1971-01	txt
Low-Pressure Distillation of a Portion of the Fuel Carrier Salt from the MSRE	ORNL-4577	1971-08	txt
Corrosion in Polythermal Loop Systems: Part II	ORNL-4575	1971-06	txt
Molten-Salt Fluoride Volatility Pilot Plant	ORNL-4574	1971-04	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1970	ORNL-4548	1970-08	txt
Conceptual Design Study of a Single-Fluid Molten-Salt Breeder Reactor	ORNL-4541	1971-06	txt
Two-Fluid Molten-Salt Breeder Reactor Design Study	ORNL-4528	1970-08	txt
Encapsulation of Noble Fission Product Gases in Solid Media	ORNL-4473	1970-02	txt
Siting of Fuel Reprocessing Plants and Waste Management Facilities	ORNL-4451	1970-07	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1969	ORNL-4449	1970-02	txt
Low-Pressure Distillation of Molten Fluoride Mixtures	ORNL-4434	1971-01	txt
Liquid-Vapor Equilibria in LiF-BeF2 and LiF-BeF2-ThF4 Systems	ORNL-4415	1972-11	txt
Disposal of Solid Waste from Fuel Reprocessing by Fluidized-Bed Fluoride Volatility	ORNL-4415	1969-12	txt
Analysis of Transients in the MSRE System with 233U Fuel	ORNL-4397	1969-06	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1969	ORNL-4396	1969-08	txt
Gas Transport in MSRE Moderator Graphite: Parts II and III	ORNL-4389	1969-05	txt
Preparation of Enriching Salt 7LiF-233UF4 for Refueling the Molten Salt Reactor	ORNL-4371	1969-03	txt
Temperature Profiles within Cylinders Containing Internal Heat Sources	ORNL-4345	1969-01	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1968	ORNL-4344	1969-02	txt
Mechanical Properties of Artificial Graphites--A Survey Report	ORNL-4327	1968-12	txt
An EMF Study of LiF-BeF2 Solutions	ORNL-4257	1968-07	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 29, 1968	ORNL-4254	1968-08	txt
Zero-Power Physics Experiments on the MSRE	ORNL-4233	1968-02	txt
Fluorination of Falling Droplets of Molten Fluoride Salt as a Means of Recovering Uranium and Plutonium	ORNL-4224	1968-11	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1967	ORNL-4191	1967-12	txt
Gas Transport in MSRE Moderator Graphite: Part I	ORNL-4148	1967-09	txt
MSRE Control Elements: Manufacture, Inspection, Drawings and Specifications	ORNL-4123	1967-07	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1967	ORNL-4119	1967-07	txt
Reactor Chemistry Division: Annual Progress Report for Period Ending December 31, 1966	ORNL-4076	1967-03	txt
Development of a Model for Computing 135Xe Migration in the MSRE	ORNL-4069	1967-06	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1966	ORNL-4037	1967-01	txt
Design Studies of 1000 MWe Molten-Salt Breeder Reactors	ORNL-3996	1966-08	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1966	ORNL-3936	1966-06	txt
Reactor Chemistry Division: Annual Progress Report for Period Ending December 31, 1965	ORNL-3913	1966-03	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1965	ORNL-3872	1965-12	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1965	ORNL-3812	1965-05	txt
Rare-Earth Halides	ORNL-3804	1965-05	txt
Preliminary Design Study of a Continuous Fluorination-Vacuum Distillation System for an MSBR	ORNL-3791	1966-01	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending July 31, 1964	ORNL-3708	1964-11	txt
Influence of Several Metallurgical Variables on the Tensile Properties of Hastelloy N	ORNL-3661	1964-08	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending January 31, 1964	ORNL-3626	1964-05	txt
Adaptation of the Fused-Salt Fluoride-Volatility Process to the Recovery of Uranium from Al-U Alloy Fuel	ORNL-3596	1964-06	txt
Molten-Salt Solvents for Fluoride Volatility Processing of Al-Matrix Nuclear Fuel Elements	ORNL-3594	1964-08	txt
Mechanical Properties of Some Refractory Metals and their Alloys	ORNL-3593	1964-04	txt
Reduction of UF6 Retention on Beds of MgF2 Used for Removal of TcF6	ORNL-3544	1964-01	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending July 31, 1963	ORNL-3529	1963-12	txt
Fabrication of the Heat Exchanger Tube Bundle for the MSRE	ORNL-3500	1963-11-22	txt
Review of Thorium Reserves in Granitic Rock and Processing of Thorium Ores	ORNL-3495	1963-11-22	txt
An Experimental Study of Sorption of UF6 by NaF Pellets	ORNL-3494	1963-11-14	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending January 31, 1963	ORNL-3419	1963-05	txt
Review of Electronic Absorption Spectra of Molten Salts	ORNL-3411	1963-08-13	txt
Mixtures of Metals with Molten Salts	ORNL-3391	1963-08	txt
Thermal Analysis of Fused Salt Phase Equilibria	ORNL-3373	1962-12	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1962	ORNL-3369	1962-12	txt
Recovery of PuF6 by Fluorination of Fused Fluoride Salts	ORNL-3298	1962-09	txt
Thermodynamic Properties of Molten-Salt Solutions	ORNL-3293	1962-10-12	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1962	ORNL-3282	1962-07	txt
Corrosion of Mark-1 INOR-8 Hydrofluorinator and Mark III Nickel Fluorinator after 14 Dissolution Runs	ORNL-3253	1962-02-09	txt
Aircraft Nuclear Propulsion Program: Semiannual Progress Report for Period Ending April 30, 1961	ORNL-3144	1961-07-11	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1961	ORNL-3215	1961-12	txt
INOR-8-Graphite-Fused Salt Compatibility Test	ORNL-3124	1961-06-01	txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1961	ORNL-3122	1961-06	txt
Aircraft Nuclear Propulsion Program: Semiannual Progress Report for Period Ending October 31, 1960	ORNL-3029	1960-12-16	txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending July 31, 1960	ORNL-3014	1960-12	txt
The Feasibility of an Unattended Nuclear Power Plant	ORNL-2985	1960-09	txt
Self-Diffusion of Chromium in Nickel-Base Alloys	ORNL-2982	1961-01-20	txt
Molten-Salt Reactor Program: Quarterly Progress Report for Periods Ending January 31 and April 30, 1960	ORNL-2973	1960-09	txt
Aircraft Nuclear Propulsion Program: Semiannual Progress Report for Period Ending April 30, 1960	ORNL-2942	1960-07-12	txt
Phase Equilibria in Molten-Salt Breeder Reactor Fuels	ORNL-2896	1960-12	txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending October 31, 1959	ORNL-2890	1960-03	txt
Aircraft Nuclear Propulsion Program: Semiannual Progress Report for Period Ending October 31, 1959	ORNL-2840	1959-10	txt
Corrosion Associated with Hydrofluorination in the ORNL Fluoride Volatility Process	ORNL-2833	1961-11-01	txt
Corrosion Associated with Fluorination in the ORNL Fluoride Volatility Process	ORNL-2832	1961-06	txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending July 31, 1959	ORNL-2799	1959-10	txt
Experimental Molten-Salt-Fueled 30 MWe Power Reactor	ORNL-2796	1960-03-08	txt
Mechanical Properties of INOR-8	ORNL-2780	1961-01-10	txt
Welding of Nickel-Molybdenum Alloys	ORNL-2760	1959-08-11	txt
Characteristics of Spherical, Homogeneous, Two-Region, Molten-Fluoride-Salt Reactors	ORNL-2751	1959-09-16	txt
Solubility Relations Among Rare-Earth Fluorides in Selected Molten-Salt Solvents	ORNL-2749	1959-10-13	txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending April 30, 1959	ORNL-2723	1959-06	txt
Phase Equilibria in the System UF4-ThF4 and LiF-UF4-ThF4	ORNL-2719	1959-08-17	txt
Aircraft Nuclear Propulsion Program: Semiannual Progress Report for Period Ending March 31, 1959	ORNL-2711	1959-03	txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending January 31, 1959	ORNL-2684	1959-03	txt
Aluminum Chloride as a Thermodynamic Working Fluid and Heat Transfer Medium	ORNL-2677	1959-09	txt
The Fused-Salt/Fluoride Volatility Process for Recovering Uranium	ORNL-2661	1959-04	txt
Measurements Through a Hot Cell Window Using Optical Tooling	ORNL-2658	1959-04	txt
Molten-Salt Reactor Program Status Report	ORNL-2634	1958-12	txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending October 31, 1958	ORNL-2626	1959-01	txt
Gas-Cooled, Molten-Salt Heat Exchanger Design Study	ORNL-2605	1959-10	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 30, 1958	ORNL-2599	1958-09	txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending June 30, 1958	ORNL-2551	1958-09-10	txt
Phase Diagrams of Nuclear Reactor Materials	ORNL-2548	1959-11	txt
A Zero-Power Reflector-Moderated Reactor Experiment at Elevated Temperature	ORNL-2536	1958-08-01	txt
Solubility and Stability of PuF3 in Fused-Alkali-Fluoride-Beryllium Fluoride Mixtures	ORNL-2530	1959-11	txt
Influence of Composition upon the 1500F Creep-Rupture Strength and Microstructure of Mo-Cr-Fe-Ni-Base Alloys	ORNL-2524	1959-11	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 31, 1958	ORNL-2517	1958-08-20	txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending January 31, 1958	ORNL-2474	1958-05	txt
Termination Report for Construction of the ART Facility	ORNL-2465	1958-11-21	txt
ART Removal and Disassembly	ORNL-2464	1960-03-04	txt
Thermal Stress Analysis of the ART Heat Exchanger Channels and Header Pipes	ORNL-2442	1958-03-14	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 31, 1957	ORNL-2440	1958-04-15	txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending October 31, 1957	ORNL-2431	1958-02-07	txt
Guide to the Phase Diagrams of the Fluoride Systems	ORNL-2396	1959-11	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 30, 1957	ORNL-2387	1958-02	txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending September 1, 1957	ORNL-2378	1957-12-27	txt
ART Fuel Pump and Xenon Removal System Development, Test Evaluation, and Aircraft Application	ORNL-2376	1957-12-10	txt
Some Aspects of the Behavior of Fission Products in Molten-Fluoride Reactor Fuels	ORNL-2374	1957-08-28	txt
Effect of Radiation on Corrosion of Structural Materials by Molten Fluorides	ORNL-2373	1957-08-13	txt
Shield Plug Assembly for the ART Fuel Pumps	ORNL-2353	1958-04-03	txt
Aircraft Reactor Experiment - Metallurgical Aspects	ORNL-2349	1957-12-20	txt
Components of the Fused-Salt and Sodium Circuits of the ARE	ORNL-2348	1958-02-15	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 30, 1957	ORNL-2340	1957-09-11	txt
Interim Report on Corrosion by Zirconium-Base Fluorides	ORNL-2338	1961-01-03	txt
Interim Report on Corrosion by Alkali-Metal Fluorides: Work to May 1, 1953	ORNL-2337	1959-03-20	txt
Phase Equilibrium Diagrams for Fused Salt Systems	ORNL-2295	1957-06-24	txt
Viscosity Measurements on Molten Fluoride Mixtures	ORNL-2278	1957-06-28	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 31, 1957	ORNL-2274	1957-07-05	txt
Inconel as a Structural Material for a High-Temperature Fused-Salt Reactor	ORNL-2264	1957-06-04	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 31, 1956, part 6	ORNL-2221	1957-03-26	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 31, 1956, part 1-5	ORNL-2221	1957-03-12	txt
Investigation of Fluid Flow in the ART and Other Reflector-Moderator Reactor Cores	ORNL-2199	1957-04	txt
Analytical and Experimental Studies of the Temperature Structure Within the ART Core	ORNL-2198	1957-01-31	txt
Optical Properties and X-Ray Diffraction Data for Some Inorganic Fluoride and Chloride Compounds	ORNL-2192	1958-10-23	txt
Dissolution of U-Zr Fuel Elements in Fused NaF-ZrF4	ORNL-2183	1957-01-24	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1956	ORNL-2157	1956-12	txt
Corrosion Products Formed in the Reaction Between Fused Sodium Hydroxide and Iron-Rich Alloys of Fe, Cr, and Ni	ORNL-2156	1957-04-26	txt
A Physical Property Summary for ANP Fluoride Mixtures	ORNL-2150	1956-08-23	txt
Measurement and Analysis of the Holdup of Gas Mixtures by Charcoal Traps	ORNL-2116	1956-07-27	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1956	ORNL-2106	1956-09	txt
Compatibility Tests of Materials for Use in Bearings, Seals, and Valves in Fused Fluoride Salts at 1200F	ORNL-2103	1956-09-21	txt
Design Report on the Aircraft Reactor Test	ORNL-2095	1956-05	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1956	ORNL-2061	1956-05-23	txt
Corrosion of Materials in Fused Hydroxides	ORNL-2048	1956-03	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1955	ORNL-2012	1956-02-20	txt
Steady-State Control Characteristics of Chemical-Nuclear Aircraft Power Plants	ORNL-1976	1956-02-29	txt
A Fluoride Fuel In-Pile Loop Experiment	ORNL-1965	1957-01-15	txt
Enthalpies and Heat Capacities of Solid and Molten Fluoride Mixtures	ORNL-1956	1956-01-11	txt
Fabrication of Heat Exchangers and Radiators for High-Temperature Reactor Applications	ORNL-1955	1956-06-14	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1955	ORNL-1947	1955-10	txt
Application of Temperature Solutions for Forced Convection Systems with Volume Heat Sources	ORNL-1933	1955-09-29	txt
A Theoretical Study of 135Xe Poisoning Kinetics in Fluid-Fueled, Gas-Sparged Nuclear Reactors	ORNL-1924	1956-02-06	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1955	ORNL-1896	1955-07	txt
Disassembly and Postoperative Examination of the Aircraft Reactor Experiment	ORNL-1868	1959-04-02	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1955	ORNL-1864	1955-04-21	txt
Operation of the Aircraft Reactor Experiment	ORNL-1845	1955-09	txt
Aircraft Reactor Test Hazards Summary Report	ORNL-1835	1955-01	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1954	ORNL-1816	1955-01	txt
Some Economic Aspects of Thorium Breeder Reactors	ORNL-1810	1955-10-12	txt
Design Calculations for a Miniature High-Temperature In-Pile Circulating Fuel Loop	ORNL-1808	1955-09-19	txt
Fused Salt Heat Transfer Part 2: Forced Convection Heat Transfer in FLiNaK	ORNL-1777	1955-02-01	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1954	ORNL-1771	1954-10	txt
Preliminary Critical Assemblies of the Reflector Moderator Reactor	ORNL-1770	1954-11-22	txt
Free Convection in Fluids Having a Volume Heat Source	ORNL-1769	1954-11-15	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1954	ORNL-1729	1954-07	txt
ORNL Aircraft Nuclear Power Plant Designs	ORNL-1721	1954-05	txt
Turbulent Heat Transfer from a Molten Fluoride Salt Mixture to NaK in a Double-Tube Heat Exchanger	ORNL-1716	1954-11-08	txt
Optical Properties of Some Inorganic Fluoride and Chloride Compounds	ORNL-1712	1954-05-05	txt
Present Status of the Investigation of Aqueous Solutions Suitable for a Thorium Breeder Blanket	ORNL-1711	1954-05-10	txt
A Summary of Density Measurements on Molten Fluoride Mixtures and a Correlation for Predicting Densities	ORNL-1702	1954-07-19	txt
Forced Convection Heat Transfer Between Parallel Plates and in Annuli with Volume Heat Sources within the Fluids	ORNL-1701	1954-05-11	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1954	ORNL-1692	1954-04	txt
Enthalpies and Specific Heats of Alkali and Alkaline-Earth Hydroxides at High Temperatures	ORNL-1653	1954-01-07	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1953	ORNL-1649	1954-01	txt
Preliminary Critical Assembly for the Aircraft Reactor Experiment	ORNL-1634	1953-10-18	txt
Critical Experiments on Direct Cycle Aircraft Reactor	ORNL-1615	1953-10-22	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1953	ORNL-1609	1953-10	txt
Chemical Methods for the Separation of Lithium Isotopes	ORNL-1592	1953-08-18	txt
Heavy Isotope Buildup in Core of 233U Breeder	ORNL-1567	1953-10-06	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1953	ORNL-1556	1953-07	txt
Thermodynamic and Heat Transfer Analysis of the Aircraft Reactor Experiment	ORNL-1535	1953-08-10	txt
The Moderator Cooling System for the Reflector-Moderated Reactor	ORNL-1517	1954-01-22	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1953	ORNL-1515	1953-04	txt
General Information Concerning Hydroxides	ORNL-1495	1953-03	txt
Corrosion by Molten Fluorides	ORNL-1491	1953-03-17	txt
General Information Concerning Fluorides	ORNL-1490	1953-02-27	txt
Methods of Fabrication of Control and Safety Element Components for the ARE and HRE	ORNL-1463	1953-02-26	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1952	ORNL-1439	1953-01	txt
Aircraft Reactor Experiment Hazards Summary Report	ORNL-1407	1952-11	txt
Forced Convection Heat Transfer in Pipes with Volume Heat Sources within the Fluids	ORNL-1395	1952-12	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1952	ORNL-1375	1952-11	txt
Turbulent Forced Convection Heat Transfer in Circular Tubes containing Molten Sodium Hydroxide	ORNL-1370	1952-10	txt
Some Effects of Transmutation Products on U233 Breeder Pile Operation	ORNL-1368	1952-09-23	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1952	ORNL-1294	1952-08	txt
A Design Study of a Nuclear-Powered Airplane in which Circulating Fuel is Piped Directly	ORNL-1287	1953-03-31	txt
General Information Concerning Fluorides	ORNL-1252	1952-02-19	txt
Reactor Program of the Aircraft Nuclear Propulsion Project	ORNL-1234	1952-06-02	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1952	ORNL-1227	1952-05	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1951	ORNL-1170	1952-02	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1951	ORNL-1154	1951-12	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1951	ANP-65	1951-06	txt
An Investigation of ThF4-Fused-Salt Solutions for Homogeneous Breeder Reactors	ORNL-1030	1951-06-19	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1951	ANP-60	1953-03	txt
Dry Fluoride Process Status Report	ORNL-0980	1951-03-27	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1950	ORNL-0919	1951-02-26	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending August 1, 1950	ORNL-0858	1950-12-05	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending May 31, 1950	ORNL-0768	1950-08-14	txt
The Atomic Powered Aircraft, January 1950	ORNL-0684	1950-04-26	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending February 28, 1950	ORNL-0629	1950-02	txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending November 30, 1949	ORNL-0528	1950-01	txt

ORNL Technical Memoranda Related to the Molten-Salt Reactor Program

report	filename	date	ocr
Disposition Options for Uranium-233	ORNL-TM-13553	1999-06	txt
Strategy for the Future Use and Disposition of Uranium-233	ORNL-TM-13552	1998-04	txt
Isotopic Dilution Requirements for 233U Criticality Safety in Processing and Disposal Facilities	ORNL-TM-13524	1997-11	txt
Definition of Weapons-Usable Uranium-233	ORNL-TM-13517	1998-03	txt
A Descriptive Model of the MSRE After Shutdown	ORNL-TM-13142	1996-01	txt
Materials Considerations for Molten-Salt Accelerator-Based Pu Conversion Systems	ORNL-TM-12925	1995-03	txt
Tensile and Creep Tests on a Single Heat of Alloy 800H	ORNL-TM-12436	1993-09	txt
Use of the MCM for Analysis of Alloy 800H Rupture Data	ORNL-TM-12430	1993-09	txt
Final Analysis of ORNL Creep-Rupture and Tensile Data on 2.25 Cr-1 Mo Steel	ORNL-TM-12429	1993-10	txt
Literature Information Applicable to the Reaction of Uranium Oxides with Chlorine to Prepare Uranium Tetrachloride	ORNL-TM-11955	1992-02	txt
Reaction of Uranium Oxides with Chlorine and Carbon or CO to Prepare Uranium Chlorides	ORNL-TM-11792	1991-11	txt
Nuclear Power Options Viability Study--Volume I: Executive Summary	ORNL-TM-9780-V1	1986-09	txt
Nuclear Power Options Viability Study--Volume II: Reactor Concepts, Descriptions, and Assessments	ORNL-TM-9780-V2	1986-09	txt
Nuclear Power Options Viability Study--Volume III: Nuclear Discipline Topics	ORNL-TM-9780-V3	1986-09	txt
Nuclear Power Options Viability Study--Volume IV: Bibliography	ORNL-TM-9780-V4	1986-09	txt
Extended Storage-in-Place of MSRE Fuel Salt and Flush Salt	ORNL-TM-9756	1985-09	txt
Mechanical Properties of Inconel 617 and 618	ORNL-TM-9337	1985-02	txt
Thermal-Convection-Loop Study of the Corrosion of Fe-Ni-Cr Alloys by Molten NaNO3-KNO3	ORNL-TM-8298	1982-12	txt
Conceptual Design Characteristics of a Denatured Molten-Salt Reactor with Once-Through Fueling	ORNL-TM-7207	1980-07	txt
Molten Salt Processes Applied to Ceramic Fuels	ORNL-TM-6763	1979-06	txt
Radiological Assessment of Thorium Mining and Milling	ORNL-TM-6474	1978-10	txt
Development Status and Potential Program for Development of Proliferation-Resistant Molten-Salt Reactors	ORNL-TM-6415	1979-03	txt
Molten-Salt Reactors for Efficient Nuclear Fuel Utilization without Plutonium Separation	ORNL-TM-6413	1978-08	txt
Thermodynamics of Carbon in Nickel-Based Multicomponent Solid Solutions	ORNL-TM-6282	1978-04	txt
Status of Tellurium-Hastelloy-N Studies in Molten-Fluoride Salts	ORNL-TM-6002	1977-10	txt
Expansion Potential for Existing Nuclear Power Station Sites	ORNL-TM-5927	1977-11	txt
Status of Materials Development for Molten-Salt-Reactors	ORNL-TM-5920	1978-01	txt
Compatibility Studies of Potential Molten-Salt Breeder Reactor Materials in Molten Fluoride Salts	ORNL-TM-5783	1977-05	txt
The Corrosion of Type 316 Stainless Steel to Li2BeF4	ORNL-TM-5782	1977-04	txt
Corrosion of Several Metals in Supercritical Steam at 538 C	ORNL-TM-5781	1977-05	txt
Distribution and Behavior of Tritium in the Coolant-Salt Technology Facility	ORNL-TM-5759	1977-04	txt
Importance of Billet Microstructure in the Hot Extrusion of 2% Ti-Hastelloy N	ORNL-TM-5741	1977-05	txt
Production of Homogeneous Titanium-Hastelloy N Alloys	ORNL-TM-5697	1977-02	txt
Survey of Technology for Storage of Thermal Energy in Heat Transfer Salt	ORNL-TM-5682	1977-01	txt
Assessment of the Thorium Fuel Cycle in Power Reactors	ORNL-TM-5565	1977-01	txt
System Design Description of Forced-Convection Molten-Salt Corrosion Loops MSR-FCL-3 and MSR-FCL-4	ORNL-TM-5540	1976-11	txt
Temperature Gradient Compatibility Tests of Some Refractory Metals and Alloys in Bi and Bi-Li Solutions	ORNL-TM-5503	1976-11	txt
Heat Transfer Measurements in a Forced Convection Loop with Two Molten-Fluoride Salts	ORNL-TM-5335	1976-10	txt
Evaluation of Alternate Secondary (and Tertiary) Coolants for the MSBR	ORNL-TM-5325	1976-04	txt
Conceptual Design of a Continuous Fluorinator Experimental Facility (CFEF)	ORNL-TM-5253	1976-07	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 23	ORNL-TM-5252	????-??	txt
A Study of Tritium Removal from Fusion Reactor Blankets of Molten-Salt and Lithium-Aluminum	ORNL-TM-5104	1976-03	txt
On Nuclear Fuel, Mass Balances, Conversion Ratio, Doubling Time, and Uncertainty	ORNL-TM-5050	1976-11	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 21	ORNL-TM-4894	1976-03	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 20	ORNL-TM-4870	1976-01	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 19	ORNL-TM-4863	1975-07	txt
A Method for Calculating the Steady-State Distribution of Tritium in an MSBR Plant	ORNL-TM-4804	1975-04	txt
The Molten-Salt Reactor Information System	ORNL-TM-4802	1975-06	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 18	ORNL-TM-4698	1975-03	txt
Corrosion of Several Iron and Nickel-Base Alloys in Supercritical Steam at 1000F	ORNL-TM-4552	1974-08	txt
Influence of Aging on the Impact Properties of Hastelloy N	ORNL-TM-4380	1973-12	txt
Density and Viscosity of Several Molten Fluoride Mixtures	ORNL-TM-4308	1973-03	txt
Alloy Compatibility with LiF-BeF2 Salts Containing ThF4 and UF4	ORNL-TM-4286	1972-12	txt
Compatibility of Brazing Alloys and the Molten Salt NaBF4-NaF at 610 C	ORNL-TM-4272	1972-12	txt
Mass Transfer Between Hastelloy-N and a Molten NaBF4 Mixture in a Thermal Convection Loop	ORNL-TM-4271	1972-12	txt
A Forced-Circulation Loop for Corrosion Studies: Hastelloy-N Compatibility with NaBF4-NaF	ORNL-TM-4221	1972-12	txt
MRPP - Multi-Region Processing Plant Code	ORNL-TM-4210	1976-09	txt
Evaluation of Hastelloy-N Alloys After Nine Years Exposure to Both a Molten Fluoride Salt and Air	ORNL-TM-4189	1972-12	txt
Effect of FeF2 Addition on Mass Transfer in a Hastelloy N/LiF-BeF2-UF4 Thermal Convection Loop System	ORNL-TM-4188	1972-12	txt
Improved Representation of Some Aspects of Circulating-Fuel Reactor Kinetics	ORNL-TM-4179	1973-05	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 17	ORNL-TM-4178	????-??	txt
Post-Irradiation Examination of Materials from the MSRE	ORNL-TM-4174	1972-12	txt
Influence of Various Alloying Additions on the Strength of Nickel-Base Alloys	ORNL-TM-4173	1972-12	txt
Corrosion of Type 304L Stainless Steel and Hastelloy-N by Mixtures of BF3, Air, and Argon	ORNL-TM-4172	1972-12	txt
Development of a Venturi-Type Bubble Generator for Use in the MSR Xenon Removal System	ORNL-TM-4122	1972-12	txt
Forced-Convection Heat-Transfer Measurements with a Molten Fluoride Mixture Flowing in a Smooth Tube	ORNL-TM-4079	1973-03	txt
The Equilibrium of Dilute UF3 Solutions Contained in Graphite	ORNL-TM-4056	1972-12	txt
Molten Salts as Blanket Fluids in Controlled Fusion Reactors	ORNL-TM-4047	1972-12	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 16	ORNL-TM-4020	????-??	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 15	ORNL-TM-4019	????-??	txt
Neutron-Induced Transmutation of High-Level Radioactive Waste	ORNL-TM-3964	1972-12	txt
Zero Power Experiments with 233U in the MSRE	ORNL-TM-3963	1972-12	txt
MSR Component Replacements Using Remote Cutting and Welding Techniques	ORNL-TM-3939	1972-12	txt
The Migration of a Class of Fission Products (Noble Metals) in the MSRE	ORNL-TM-3884	1972-12	txt
Corrosion and Mass Transfer Characteristics of NaBF4-NaF in Hastelloy-N	ORNL-TM-3866	1972-10	txt
Design and Operation of a Forced-Circulation Corrosion Test Facility Employing Hastelloy-N and NaBF4 Salt	ORNL-TM-3863	1973-01	txt
Design Studies of a Molten-Salt Reactor Demonstration Plant	ORNL-TM-3832	1972-06	txt
Heat Transfer Salt for High-Temperature Steam Generation	ORNL-TM-3777	1972-12	txt
Hybrid Computer Simulation of the MSBR	ORNL-TM-3767	1972-05-05	txt
Estimated Behavior of Titanium in MSBR Chemical Processing Systems	ORNL-TM-3763	1972-04	txt
Mass Transfer Between Small Bubbles and Liquids in Cocurrent Turbulent Pipeline Flow	ORNL-TM-3718	1972-04	txt
A Study of the Adherence of Tungsten and Molybdenum Coatings	ORNL-TM-3609	1971-12	txt
Indexed Abstracts of Selected References on Molten-Salt Reactor Technology	ORNL-TM-3595	1971-12	txt
Design and Cost Study of a Fluorination-Reductive Extraction-Metal Transfer Processing Plant for the MSBR	ORNL-TM-3579	1972-05	txt
Availability of Natural Resources for Molten-Salt Breeder Reactors	ORNL-TM-3563	1971-11	txt
Remote Inspection of Welded Joints	ORNL-TM-3561	1971-09	txt
The Long-Term Hazard of Radioactive Wastes Produced by Enriched Uranium, U/Pu, and Th/U Fuel Cycles	ORNL-TM-3548	1971-11	txt
Solution of the Equation Describing the Interface Between Two Fluids for Volume and Pressure Between Drops	ORNL-TM-3528	1971-08	txt
Operation of the Sampler-Enricher in the MSRE	ORNL-TM-3524	1971-10	txt
Status of Noble-Gas Removal and Disposal	ORNL-TM-3515	1971-08	txt
Mass Transfer Between Hastelloy-N and Haynes Alloy No. 25 in a Molten Sodium Fluoroborate Mixture	ORNL-TM-3488	1971-10	txt
Xenon Behavior in the MSRE	ORNL-TM-3464	1971-10	txt
Estimated Cost of Adding a Third Salt-Circulation Loop for Controlling Tritium Migration in the 1000-MWe MSBR	ORNL-TM-3428	1971-07	txt
ROD: A Nuclear and Fuel-cycle Analysis Code for Circulating-Fuel Reactors	ORNL-TM-3359	1971-09	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 10	ORNL-TM-3352	1972-12	txt
Experience with Sodium Fluoroborate Circulation in an MSRE-Scale Facility	ORNL-TM-3344	1972-09	txt
Thermal Stability of Titanium-Modified Hastelloy-N at 650 and 760 C	ORNL-TM-3321	1971-07	txt
Further Discussion of Instrumentation and Controls Development Needed for the MSBR	ORNL-TM-3303	1971-08	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 9	ORNL-TM-3259	1972-12	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 8	ORNL-TM-3258	1972-05	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 7	ORNL-TM-3257	1972-02-10	txt
MSRE Procedures for the Period Between Examination and Ultimate Disposal	ORNL-TM-3253	1971-02	txt
Fluid Dynamic Studies of the MSRE Core	ORNL-TM-3229	1970-11	txt
Molten-Salt Breeder Experiment Design Bases	ORNL-TM-3177	1970-11	txt
A Study of Fission Products in the Molten-Salt Reactor Experiment by Gamma Spectrometry	ORNL-TM-3151	1972-08	txt
Thermal Radiation Transfer of Afterheat in MSBR Heat Exchangers	ORNL-TM-3145	1971-03	txt
Fluorine Production and Recombination in Frozen MSR Salts after Reactor Operation	ORNL-TM-3144	1970-09	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 6	ORNL-TM-3141	1971-12	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 5	ORNL-TM-3140	1971-10	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 4	ORNL-TM-3139	1971-08	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 3	ORNL-TM-3138	1971-05	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 2	ORNL-TM-3137	1971-02	txt
MSBR Control Studies: Analog Simulation Program	ORNL-TM-3102	1971-05	txt
Influence of Ti, Zr, and Hf Additions on the Resistance of Modified Hastelloy-N to Irradiation Damage	ORNL-TM-3064	1971-01	txt
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - Fourth Group	ORNL-TM-3063	1971-03	txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 1	ORNL-TM-3053	1970-11	txt
MSRE Operator Training and Operating Techniques	ORNL-TM-3041	1973-08	txt
MSRE Systems and Components Performance	ORNL-TM-3039	1973-06	txt
Spray, Mist, Bubbles, and Foam in the MSRE	ORNL-TM-3027	1970-06	txt
An Extended Hydraulic Model of the MSRE Circulating Fuel System	ORNL-TM-3007	1970-06	txt
Reactor Power Measurement and Heat Transfer Performance in the MSRE	ORNL-TM-3002	1970-05	txt
Quality-Assurance Practices in Construction and Maintenance of the MSRE	ORNL-TM-2999	1970-04	txt
Experimental Dynamic Analysis of the MSRE with 233U Fuel	ORNL-TM-2997	1970-04	txt
Development of Fuel- and Coolant-Salt Centrifugal Pumps for the MSRE	ORNL-TM-2987	1970-10	txt
Compatibility of Fused Sodium Fluoroborate and BF3 Gas with Hastelloy-N Alloys	ORNL-TM-2978	1970-06	txt
Plans for Post-Operation Examination of the MSRE	ORNL-TM-2974	1970-04-07	txt
Calculated Radioactivity of MSRE Fuel Salt	ORNL-TM-2970	1970-05	txt
A New Approach to a Design of Steam Generators for Molten Salt Reactor Power Plants	ORNL-TM-2953	1971-06	txt
Parametric Survery of the Effects of Major Parameters of the Design of MSBR Heat Exchangers	ORNL-TM-2952	1971-11	txt
Control Studies of a 1000-MWe MSBR	ORNL-TM-2927	1970-05	txt
Tensile Properties of Hastelloy-N Welded After Irradiation	ORNL-TM-2858	1970-04	txt
Frequency-Response Testing of the Molten-Salt Reactor Experiment	ORNL-TM-2823	1970-03	txt
Computer Programs for MSBR Heat Exchangers	ORNL-TM-2815	1971-04	txt
Preliminary Systems Design Description of the Salt Pump Test Stand for the MSBE	ORNL-TM-2780	1969-12	txt
Design and Construction of Core Irradiation-Specimen Array for MSRE Runs 19 and 20	ORNL-TM-2743	1969-12	txt
Catastropic Corrosion of Type 304 Stainless Steel in a System Circulating Fused Sodium Fluoroborate	ORNL-TM-2741	1970-01	txt
Mechanical Behavior of Artificial Graphites as Portrayed by Uniaxial Tests	ORNL-TM-2727	1969-12	txt
Compatibility of Molybdenum-Base Alloy TZM with LiF-BeF2-ThF4-UF4 at 1100 C	ORNL-TM-2724	1969-12	txt
Feasibility Study of Remote Cutting and Welding for Nuclear Plant Maintenance	ORNL-TM-2712	1969-11	txt
Assessment of Molten Salts as LMFBR Intermediate Coolants	ORNL-TM-2696	1969-09-03	txt
Inherent Neutron Source in MSRE with Clean 233U Fuel	ORNL-TM-2685	1969-08	txt
Management of Noble-Gas Fission-Product Wastes from Reprocessing Spent Fuels	ORNL-TM-2677	1969-11	txt
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - Third Group	ORNL-TM-2647	1970-01	txt
Conceptual System Design Description of the Salt Pump Test Stand for the MSBE	ORNL-TM-2643	1969-08	txt
Fractional Crystallization Reactions in the System LiF-BeF2-ThF4	ORNL-TM-2596	1969-07-08	txt
Processing of the MSRE Flush and Fuel Salts	ORNL-TM-2578	1969-08	txt
Theoretical Dynamic Analysis of the MSRE with 233U Fuel	ORNL-TM-2571	1969-07	txt
Materials for Molten-Salt Reactors	ORNL-TM-2511	1969-05	txt
Compatibility of Hastelloy-N and Croloy-9M with NaBF4-NaF-KBF4 Fluoroborate Salt	ORNL-TM-2490	1969-04	txt
MSBR Control Studies	ORNL-TM-2489	1969-06-02	txt
Extraction of U, Th, and Rare Earths from Molten LiF-BeF2 into Liquid Li-Bi Solutions	ORNL-TM-2486	1969-03	txt
Pre- and Post-Irradiation Mechanical Properties of Hastelloy-N Welds	ORNL-TM-2483	1969-03	txt
Design, Construction, and Testing of a Large Molten Salt Filter	ORNL-TM-2478	1969-03	txt
Dynamic Analysis of a Salt Supercritical Water Heat Exchanger and Throttle used with MSRE	ORNL-TM-2405	1969-01	txt
Diffusion of Titanium in Modified Hastelloy-N	ORNL-TM-2392	1969-01	txt
Bubbles, Drops, and Entrainment in Molten Salts	ORNL-TM-2373	1968-12	txt
The Language of Nuclear Science	ORNL-TM-2367	1968-09-17	txt
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - Second Group	ORNL-TM-2359	1969-02	txt
Solubility of Cerium Trifluoride in Molten Mixtures of LiF, BeF2, and ThF4	ORNL-TM-2335	1969-01	txt
Determination of the Void Fraction in the MSRE Using Small Induced Pressure Perturbations	ORNL-TM-2318	1969-02-06	txt
Physical Properties of Molten-Salt Reactor Fuel, Coolant, and Flush Salts	ORNL-TM-2316	1968-08	txt
Measurement of Helium Void Fraction in the MSRE Fuel Salt using Neutron-Noise Analysis	ORNL-TM-2315	1968-08-27	txt
Postirradiation Tensile and Creep-Rupture Properties of Incoloy 800 at 700 and 760 C	ORNL-TM-2305	1968-12	txt
MSRE Design and Operations Report Part XI-A: Test Program for 233U Operations	ORNL-TM-2304	1968-09	txt
Preliminary Study of a Molten-Salt Burst Reactor	ORNL-TM-2282	1968-07-10	txt
Irradiation Behavior of Cladding and Structural Materials	ORNL-TM-2258	1968-09	txt
Chemical Feasibility of Fueling Molten-Salt Reactors with PuF3	ORNL-TM-2256	1968-06-20	txt
Removal of 135Xe from Circulating Fuel Salt of the MSBR by Mass Transfer to Helium Bubbles	ORNL-TM-2245	1968-07-23	txt
Proton Reaction Analysis for Lithium and Fluorine in Graphite using a Slit-Scanning Technique	ORNL-TM-2238	1968-07	txt
Design of an Engineering-Scale, Vacuum Distillation Experiment for MSR Fuel	ORNL-TM-2213	1968-11	txt
Electrical Conductivity of Molten Fluorides: A Review	ORNL-TM-2180	1968-03-26	txt
Fluoride Volatility for Recovering U and Pu from Spent UO2 Fuels	ORNL-TM-2170	1969-04	txt
Graphite Behavior and its Effects on MSBR Performance	ORNL-TM-2136	1969-02	txt
MSRE Design and Operations Part Report V-A: Safety Analysis of Operation with 233U	ORNL-TM-2111	1968-02	txt
Tube Vibration in MSRE Primary Heat Exchanger	ORNL-TM-2098	1968-01-03	txt
Measurement of Relative Volatilities of Rare-Earth Fluorides in Mixtures of LiF and BeF2	ORNL-TM-2058	1968-01	txt
Containers for Molten Fluoride Spectroscopy	ORNL-TM-2047	1967-11-08	txt
Effects of Irradiation on the Mechanical Properties of Hastelloy N	ORNL-TM-2043	1968-01	txt
Reduction of Iron Dissolved in Molten LiF-ThF4	ORNL-TM-2036	1967-11-02	txt
Closed-Circuit Television Viewing in Maintenance of Radioactive Systems at ORNL	ORNL-TM-2032	1967-11-01	txt
Investigation of One Concept of a Thermal Shield for the Room Housing an MSBR	ORNL-TM-2029	1967-11	txt
Corrosion Behavior of Nickel-Molybdenum Alloys in Fused Fluoride Mixtures	ORNL-TM-2021	1967-05	txt
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - First Group	ORNL-TM-1997	1967-11	txt
Experience with Hi-Temp Centrifugal Pumps and their Application to MSBRs	ORNL-TM-1993	1967-09	txt
A Literature Survey of the Fluorides and Oxyfluorides of Molybdenum	ORNL-TM-1976	1967-10	txt
Operation of Molten-Salt Convection Loops in the ORR	ORNL-TM-1960	1967-12	txt
Review of Molten-Salt Reactor Physics Calculations	ORNL-TM-1946	1967-08	txt
"MATEXP", A Program for Solving ODEs by the Matrix Exponential Method	ORNL-TM-1933	1967-08-30	txt
Corrosion of the Volatility Pilot Plant INOR-8 Dissolver	ORNL-TM-1907	1967-07-21	txt
In- and Ex-Reactor Stress-Rupture Properties of Hastelloy N Tubing	ORNL-TM-1906	1967-09	txt
Maintenance Development Program for MSBRs	ORNL-TM-1859	1967-06-30	txt
Safety Program for MSBRs	ORNL-TM-1858	1967-06-09	txt
Physics Program for MSBRs	ORNL-TM-1857	1967-06-12	txt
Instrumentation and Controls Development for MSBRs	ORNL-TM-1856	1967-05-22	txt
Components and Systems Development for MSBRs	ORNL-TM-1855	1967-06-30	txt
Materials Development for MSBRs	ORNL-TM-1854	1967-06	txt
Chemical Research and Development for MSBRs	ORNL-TM-1853	1967-06-06	txt
Fuel and Blanket Processing Development for MSBRs	ORNL-TM-1852	1967-06	txt
Summary of the Objectives, Design, and a Program of Development of MSBRs	ORNL-TM-1851	1967-06-12	txt
A Model for Computing the Migration of Very Short-Lived Noble Gases into MSRE Graphite	ORNL-TM-1810	1967-07	txt
The Reactivity Balance in the MSRE	ORNL-TM-1796	1967-03-10	txt
Considerations of Low-Pressure Distillation of MSBR Fuels	ORNL-TM-1730	1967-03	txt
Experimental Dynamic Analysis of the MSRE	ORNL-TM-1647	1966-10-13	txt
Period Measurements on the MSRE During Fuel Circulation: Theory and Experiment	ORNL-TM-1626	1966-10	txt
Tests of Various Particle Filters for Removal of Oil Mists and Hydrocarbon Vapor	ORNL-TM-1623	1966-09-07	txt
Design Study of a Heat-Exchange System for One MSBR Concept	ORNL-TM-1545	1967-09	txt
Solutions to the Problems of High-Temperature Irradiation Embrittlement	ORNL-TM-1544	1966-06	txt
Removal of Protactinium from Molten Fluoride Breeder Blanket Mixtures	ORNL-TM-1543	1966-06-01	txt
Summary of Molten-Salt Breeder Reactor Design Studies	ORNL-TM-1467	1966-03-24	txt
Simulators for Training MSRE Operators	ORNL-TM-1445	1966-04-05	txt
A Study of Lead and Lead-Salt Corrosion in Thermal-Convection Loops	ORNL-TM-1437	1966-04	txt
The Welding of New Solution-Strengthened Nickel-Base Alloys	ORNL-TM-1408	1966-04	txt
Studies of the Carbon Distribution in Hastelloy-N	ORNL-TM-1353	1966-02	txt
Elevated-Temperature Mechanical Properties of Welds in a Ni-Mo-Cr-Fe Alloy	ORNL-TM-1341	1966-01	txt
A Technique for Calculating Frequency Response and its Sensitivity to Parameter Changes	ORNL-TM-1189	1965-06-24	txt
Production of a Low-Boron Heat of Hastelloy N	ORNL-TM-1146	1965-06-11	txt
Oxide Chemistry and Thermodynamics of Molten LiF-BeF2 by Equilibriation with Gaseous H2O-HF Mixtures	ORNL-TM-1129	1965-05-07	txt
Stability Analysis of the MSRE	ORNL-TM-1070	1965-12	txt
Molten-Salt Converter Reactor: Design Study and Power Cost Estimates for a 1000 MWe Station	ORNL-TM-1060	1965-09	txt
Reconstitution of MSR Fuel by Reducing UF6 Gas to UF4 in a Molten Salt	ORNL-TM-1051	1965-03-11	txt
Tube Plugging in the MSRE Primary Heat Exchanger	ORNL-TM-1023	1965-02	txt
Tensile and Creep Properties of INOR-8 for the MSRE	ORNL-TM-1017	1965-02	txt
Effect of Elevated Temperature Irradiation on the Strength and Ductility of Hastelloy-N	ORNL-TM-1005	1965-02	txt
MSRE Neutron Source Requirements	ORNL-TM-0935	1964-09-11	txt
MSRE Design and Operations Report Part XI: Test Program	ORNL-TM-0911	1965-01	txt
MSRE Design and Operations Report Part X: Maintenance Equipment and Procedures	ORNL-TM-0910	1965-01	txt
MSRE Design and Operations Report Part IX: Safety Procedures and Emergency Plans	ORNL-TM-0909	1965-01	txt
MSRE Design and Operations Report Part VIII: Operating Procedures (Volume I)	ORNL-TM-0908A	1966-01	txt
MSRE Design and Operations Report Part VIII: Operating Procedures (Volume II)	ORNL-TM-0908B	1966-01	txt
MSRE Design and Operations Report Part VII: Fuel Handling and Processing Plant (revision)	ORNL-TM-0907REV	1968-12-28	txt
MSRE Design and Operations Report Part VII: Fuel Handling and Processing Plant	ORNL-TM-0907	1965-01	txt
Effect of Irradiation on the Bend Transition Temperatures of Mo- and Nb-Base Alloys	ORNL-TM-0880	1964-07	txt
MSRE Design and Operations Report Part VI: Operating Limits (Revision 3)	ORNL-TM-0733REV3	1969-07-25	txt
MSRE Design and Operations Report Part VI: Operating Limits (Revision 2)	ORNL-TM-0733REV2	1966-09-19	txt
MSRE Design and Operations Report Part VI: Operating Limits (Revision)	ORNL-TM-0733REV	1965-08-03	txt
MSRE Design and Operations Report Part VI: Operating Limits	ORNL-TM-0733	1965-01	txt
MSRE Design and Operations Report Part V: Reactor Safety Analysis Report	ORNL-TM-0732	1965-01	txt
MSRE Design and Operations Report Part III: Nuclear Analysis	ORNL-TM-0730	1965-01	txt
MSRE Design and Operations Report Part IIB: Nuclear and Process Instrumentation	ORNL-TM-0729B	1965-01	txt
MSRE Design and Operations Report Part IIA: Nuclear and Process Instrumentation	ORNL-TM-0729A	1965-01	txt
MSRE Design and Operations Report Part I: Description of Reactor Design	ORNL-TM-0728	1965-01	txt
Inherent Neutron Sources in Clean MSRE Fuel Salt	ORNL-TM-0611	1963-08-27	txt
Mechanical Properties of INOR-8 Cast Metal	ORNL-TM-0607	1963-08-06	txt
Design and Operation of Forced-Circulation Corrosion Testing Loops with Molten Salt	ORNL-TM-0528	1963-05-01	txt
Design Studies and Cost Estimates of Two Fluoride Volatility Plants	ORNL-TM-0522	1962-10-10	txt
MSRE Maintenance Proposal	ORNL-TM-0519	1963-03-14	txt
Radiation Chemistry of MSR System	ORNL-TM-0500	1963-03-13	txt
Analysis of Filling Accidents in MSRE	ORNL-TM-0497	1966-08-16	txt
Some Chemical Aspects of Molten-Salt Reactor Safety	ORNL-TM-0458	1962-12-14	txt
Corrosion of Nickel-Base Specimens Exposed in the Volatility Pilot Plant Mark III Fluorinator	ORNL-TM-0411	1963-01-04	txt
Prediction of Effective Yields of Delayed Neutrons in MSRE	ORNL-TM-0380	1962-10-13	txt
Temperature and Reactivity Coefficient Averaging in the MSRE	ORNL-TM-0379	1962-10-15	txt
Temperatures in the MSRE Core During Steady-State Power Operations	ORNL-TM-0378	1962-11-05	txt
Corrosion Behavior of Reactor Materials in Fluoride Salt Mixtures	ORNL-TM-0328	1962-09-19	txt
Influence of Various Gaseous Environments on the Creep-Rupture Properties of Nuclear Materials for Hi-Temp Service	ORNL-TM-0326	1962-09-19	txt
Homogenization of MSRP Fuel Samples	ORNL-TM-0291	1962-07-05	txt
576 MWt Natural Convection Molten-Salt Reactor Study	ORNL-TM-0269	1962-07-05	txt
Experimental 5 MW Thermal Convection Molten-Salt Reactor	ORNL-TM-0268	1962-07-05	txt
Xenon Diffusion in Graphite in Molten-Salt Reactors	ORNL-TM-0262	1962-06-27	txt
Safety Calculations for MSRE	ORNL-TM-0251	1962-05-15	txt
MURGATROYD--An IBM 7090 Program for the Analysis of the Kinetics of the MSRE	ORNL-TM-0203	1962-04-06	txt
Corrosion Behavior of Nickel-Molybdenum Alloys in Fused Fluoride Mixtures	ORNL-TM-0202	1969-05	txt
Development of Freeze Valve for Use in the MSRE	ORNL-TM-0128	1962-02-28	txt
Laboratory-Scale Demonstration of the Fused Salt Volatility Process	ORNL-TM-0080	1961-12-06	txt
Water Test Development of the Fuel Pump for the MSRE	ORNL-TM-0079	1962-03-27	txt
Thermal-Stress and Strain-Fatigue Analyses of the MSRE Fuel and Coolant Pump Tanks	ORNL-TM-0078	1962-10-03	txt
Catastropic Oxidation of High-Temperature Alloys	ORNL-TM-0051	1961-11-10	txt
Carbon-14 Production in Nuclear Reactors	ORNL-NUREG-TM-12	1977-02	txt
Removal of Tritium from MSBR Fuel	ORNL-MIT-117	1970-11-18	txt
Analysis and Scaleup of the Pulsed-Gas Impregnation of Graphite with Carbon	ORNL-MIT-99	1970-03-05	txt

ORNL Central Files Related to the Molten-Salt Reactor Program

report	filename	date	ocr
Decommissioning Study for the MSRE	ORNL-CF-77-391	1977-08-25	txt
Consideration of Possible Methods of Disposal of MSRE Salts	ORNL-CF-72-1-1	1972-01-28	txt
Review of Possible Choices of Secondary Coolants for MSRs	ORNL-CF-71-8-10	1971-08-06	txt
Additional Calculations of the Distribution of Tritium in the MSRE	ORNL-CF-71-7-8	1971-07-07	txt
Plans for the MSRE during the Period Between Examination and Ultimate Disposal	ORNL-CF-70-10-14	1970-10-09	txt
Critique of the MSRE: A Collection of Comments Submitted by Persons Associated with the Reactor	ORNL-CF-70-9-3	1970-09-01	txt
Calculation of Stresses During a Thermal Transient in an MSBR Outlet Nozzle	ORNL-CF-70-3-2	1970-03-02	txt
Tritium in the MSRE: Calculated Production Rates and Observed Amounts	ORNL-CF-70-2-7	1970-02-04	txt
Graphite for Molten-Salt Reactors	ORNL-CF-68-11-18	1968-11-12	txt
Performance of MSRE Nuclear Power Control Systems	ORNL-CF-68-5-11	1968-05-01	txt
Decay Heat Generation by Fission Products and 233Pa in a Single-Region MSR	ORNL-CF-68-3-38	1968-03-25	txt
Protactinium Removal from MSBR Fertile Salt	ORNL-CF-68-1-42	1968-01-24	txt
The Program Planned for the Molten-Salt Reactor Experiment	ORNL-CF-67-8-10	1967-08-01	txt
Analysis of MSRE Zero-Power Flux Noise Using Digital Techniques	ORNL-CF-66-2-67	1966-02-11	txt
Results of Neutron Fluctuation Measurements Made During the MSRE Zero-Power Experiment	ORNL-CF-65-10-18	1965-10-29	txt
Preliminary Report on Results of MSRE Zero-Power Experiments	ORNL-CF-65-8-32	1965-08-16	txt
Comparison of Calculations and Uncertainties in the Temperature Coefficients of Reactivity in the MSRE	ORNL-CF-65-3-1	1965-03-03	txt
A Literature Survey of Thermal and Physical Properties of Molten Fluoride and Chloride Salt Mixtures	ORNL-CF-63-9-20	1963-09-04	txt
Modifications to Specifications for MSRE Graphite	ORNL-CF-63-2-18	1963-02-14	txt
Preliminary Equations to Describe Iodine and Xenon Behavior in the MSRE	ORNL-CF-62-11-69	1962-11-12	txt
MSRE Analog Computer Simulation of the System with a Servo Controller	ORNL-CF-61-12-50	1961-12-26	txt
Delayed Neutron Losses in Circulating Fuel Reactors	ORNL-CF-61-10-39	1961-10-11	txt
Thorium Breeder Reactor Evaluation Part I: Fuel Yields and Cost of a MSBR	ORNL-CF-61-8-86	1961-08-18	txt
MSRE Preliminary Physics Report	ORNL-CF-61-4-62	1961-04-19	txt
MSRE Preliminary Priliminary Hazards Report	ORNL-CF-61-2-46	1961-02-28	txt
Homogeneous Molten-Salt Reactors	ORNL-CF-60-12-111	1960-12-13	txt
MSRE Radiator Design	ORNL-CF-60-11-108	1960-11-30	txt
MSRE Analog Computer Simulation of a Loss-of-Flow Accident in the Secondary System	ORNL-CF-60-11-20	1960-11-04	txt
Molten Salt Reactors: Report for 1960 Ten-Year-Plan Evaluation	ORNL-CF-60-6-97	1960-06-28	txt
Interim Report on Fluid-Fuel Thermal Breeder Reactors	ORNL-CF-60-3-31	1960-03-15	txt
Molten-Salt Breeder Reactors	ORNL-CF-59-12-64	1960-01-12	txt
Molten Salt-Graphite Compatibility Test Results	ORNL-CF-59-8-133	1959-08-31	txt
Processing of Molten Salt Power Reactor Fuel	ORNL-CF-59-2-61	1959-04-01	txt
Preliminary Study of a Graphite-Moderated Molten-Salt Power Reactor	ORNL-CF-59-1-26	1959-01-13	txt
Fuel Cycle Costs in a Graphite-Moderated Slightly-Enriched Fused-Salt Reactor	ORNL-CF-59-1-13	1959-02-24	txt
The Need for U-233 Breeding	ORNL-CF-58-12-79	1958-12-15	txt
Survey of Low-Enrichment Molten-Salt Reactors	ORNL-CF-58-10-60	1958-10-17	txt
U233 Breeders--Commentary and General Remarks	ORNL-CF-58-10-37	1958-10-08	txt
Screening Tests of Mechanical Pipe Joints for a Fused Salt Reactor System	ORNL-CF-58-8-33	1958-08-13	txt
A Molten-Salt Natural Convection Reactor System	ORNL-CF-58-2-46	1958-02-05	txt
Molten Salt Heat Transfer	ORNL-CF-58-2-40	1958-02-18	txt
Declassification of Molten Salt Reactors	ORNL-CF-57-12-29	1957-12-02	txt
Molten Salts for Civilian Power	ORNL-CF-57-10-41	1957-10-10	txt
ORSORT Study: High Performance Marine Reactor	ORNL-CF-57-8-7	1957-08	txt
Molten Fluoride Reactors	ORNL-CF-57-6-69	1957-05	txt
Maintenance of Various Reactor Types	ORNL-CF-57-4-92	1957-04-08	txt
A Preliminary Study of Molten-Salt Power Reactors	ORNL-CF-57-4-27	1957-12-03	txt
Fused Salt Power Reactor Study: Discussion Meeting 8	ORNL-CF-57-3-31	1957-03-08	txt
Fused Salt Power Reactor Study: Discussion Meeting 7	ORNL-CF-57-2-65	1957-02-14	txt
Fused Salt Power Reactor Study: Discussion Meeting 6	ORNL-CF-57-1-135	1957-01-30	txt
Power Reactor Based on Fused Salt Technology	ORNL-CF-57-1-57	1957-01-17	txt
Fused Salt Power Reactor Study: Discussion Meeting 5	ORNL-CF-56-12-101	1956-12-29	txt
Fused Salt Power Reactor Study: Discussion Meeting 4	ORNL-CF-56-12-35	1956-12-11	txt
Fused Salt Power Reactor Study: Discussion Meeting 3	ORNL-CF-56-10-110	1956-10-29	txt
Proposal for Fused Salt Power Reactor Study Group	ORNL-CF-56-9-107	1956-09-26	document missing
Fused Salt Power Reactor Study: Discussion Meeting 2	ORNL-CF-56-9-32	1956-09-11	txt
ORSORT Study: 600 MW Fused Salt Homogeneous Reactor Power Plant	ORNL-CF-56-8-208	1956-08	txt
ORSORT Study: Fused Salt Fast Breeder	ORNL-CF-56-8-204	1956-08	txt
Fused Salt Power Reactor Study: Discussion Meeting 1	ORNL-CF-56-7-114	1956-07-18	txt
Fused Salt Heat Transfer	ORNL-CF-56-5-65	1956-05-14	document missing
Molten Salt Requirements for Pratt and Whitney Aircraft	ORNL-CF-56-4-173	1956-04-26	txt
Feasibility of Molten Salt Power Reactors	ORNL-CF-56-3-117	1956-03-23	document missing
Fused Salt Processing: Problem Statement	ORNL-CF-56-2-80	1956-02-17	txt
ORSORT Study: Circulating Fluoride Reactor for a Submarine	ORNL-CF-53	1953-08-20	document missing
ORSORT Study: Fused Salt Breeder Reactor	ORNL-CF-53-10-25	1953	document missing
ORSORT Study: Reflector-Moderated, Circulating Fuel Aircraft Reactor	ORNL-CF-53-9-84	1953-08-14	txt

---

Liquid-Chloride Reactors

report	filename	date	ocr
Cursory First Look at the Molten Chloride Fast Reactor as an Alternative to the Conventional BATR Concept	MCFR_BATR	1992-04	txt
Configuration of a Molten Chloride Fast Reactor on a Thorium Fuel Cycle to Current Nuclear Fuel Cycle Concerns	MCFR_UCLA_Ottewitte_thesis	1982	txt
Molten Plutonium Chloride Fast Breeder Reactor Cooled by Molten Uranium Chloride	ANSE-1-277	1974	txt
New Boiling Salt Fast Breeder Reactor Concepts	NED-5-109	1967	txt
Fuel Properties and Nuclear Performance of Fast Reactors Fueled with Molten Chlorides	NA-3-540	1967	txt
Fission Product Effects in Molten Chloride Fast-Reactor Fuels	NSE-23-189	1965	txt
Molten-Salt Fast Reactors	ANL-6792	1963-10	txt
Thermodynamic Stability of Metals and Their Chlorides in the Presence of UCl3 and PuCl3	MSR-63-53	1963-10-31	txt
Chemical Problems of Non-Aqueous Fluid-Fuel Reactors	MIT-5001	1952-10-15	txt
Nuclear Problems of Non-Aqueous Fluid-Fuel Reactors	MIT-5000	1952-10-15	txt
An Assessment of a 2500 MWe Molten Chloride Salt Fast Reactor	AEEW-R956	1974-08	txt

---

EIR Reports

report	filename	date	ocr
Molten Chlorides Fast Breeder Reactor Problems and Possibilities	EIR-215	1972-06	txt
Molten Chlorides Fast Breeder Reactor Physics Calculations	EIR-229	1972-11	txt
High Temperature Reaction of Uranium Carbides and Transient Metal Chlorides in Molten Chloride Media	EIR-238	1973-06	txt
A Molten Salt Fast Thermal Reactor System with no Waste	EIR-249	1974-01	txt
Thorium, Uranium, other Metals and Materials from Earth's Crust Rocks	EIR-252	1974-04	txt
The Possibility of Continuous In-core Gaseous Extraction of Volatile Fission Products in a Molten Fuel Reactor	EIR-257	1974-05	txt
A High-Flux Fast Molten Salt Reactor for the Transmutation of 137Ce and 90Sr	EIR-259	1975-09	txt
Salzschmelze-Reaktorentagung in Fontenay-aux-Roses / Salt smelter reactor conference in Fontenay-aux-Roses	EIR-266	1974-10	txt
Chemical State of Sulphur Obtained by the 35Cl(n,p)35S Reaction During In-Pile Irradiation	EIR-267	1974-12	txt
Transmutation of Fission Products in a Liquid-Fuelled Fast Fission Reactor with Thermal Column	EIR-270	1975-02	txt
Breeding in Molten-Salt Reactors	EIR-276	1976-04	txt
Fast Reactors Using Molten Chloride Salts as Fuel: Final Report (1972-1977)	EIR-332	1978-01	txt
Reactor with Very Low Fission Product Inventory	EIR-411	1980-07	txt
Thermische Salzschmelzebrilter in Frankreich / Thermal molten salt filters in France	EIR-AN-HL-230	1975-06	txt
Information über die Anwendungsmöglichkeiten von Salzschmelzen in der Energiewirtschaft / Information about possible applications of salt melts in the energy industry	EIR-AN-HL-234	1975-08	txt
Kontrollblatt für externe Publikationen und Vorträge / Control sheet for external publications and lectures	EIR-AW-GL-335	1978-09	txt
Salzschmelzespeicher anstatt Hydropumpenspeicher für die Speicherung der elektrischen Energie / Molten salt storage instead of hydraulic pump storage for storing electrical energy	EIR-TM-HL-233	1974-08	txt
Synthesis and Gas Chromatography of Selected Metal Chlorides	EIR-TM-HL-235	1974-09	txt
Hochtemperatur-Wärmespeicher mit Salzschmelze und intermediärem Gaskreislauf / High-temperature heat accumulator with molten salt and intermediate gas cycle	EIR-TM-HL-238	1974-08	txt
Titrimetrische Pu-Bestimmung unter Verwendung von Cu(I)-Chlorid als Reduktionsmittel / Titrimetric Pu determination using Cu(I) chloride as reducing agent	EIR-TM-HL-255	1975-04	txt
Very high breeding ratio in the molten chloride fast power reactor with external cooling	EIR-TM-HL-261	1975-07	txt

---

Assorted Documents

report	filename	date	ocr
ORNL Review Volume 3, Number 2 - Fall 1969	ORNL-Review-v3n2	1969	txt
ORNL Review Volume 10, Number 4 - Fall 1969	ORNL-Review-v10n4	1977	txt
MSR Concepts with Reduced Potential for Proliferation of Special Nuclear Materials	ORAU-IEA-77-13	1977	txt
Catalog of Nuclear Reactor Concepts: Part I, Section III	ANL-7092	1965-09	txt
Parametric Survey of Criticality-Limited Fast Reactors Employing Uranium Fluoride Fuels	JPL-TR-32-198	1962-03-15	txt
An Evaluation of the Molten Salt Breeder Reactor	WASH-1222	1972-09	txt
Updated (1970) Cost-Benefit Analysis of the US Breeder Reactor Program	WASH-1184	1972-01	txt
Cost-Benefit Analysis of the US Breeder Reactor Program	WASH-1126	1969-04	txt
The Use of Thorium in Nuclear Power Reactors	WASH-1097	1969-06	txt
Ebasco Services 1000 MWe MSBR Conceptual Design Study	TID-26156	1972-02	txt
Sargent and Lundy Capital Cost Evaluation of 1000 MWe MSCR Power Plants	SL-1954	1962-06	txt
Report of the Fluid Fuel Reactors Task Force	TID-8507	1959-02	txt
Lithium Separation by Electrolysis	LA-1156	1950-09	txt
The Radiochemistry of Uranium, Neptunium, and Plutonium--An Updating	NAS-NS-3063	1986-02	txt
The Radiochemistry of Neptunium	NAS-NS-3060	1974-12	txt
The Radiochemistry of Plutonium	NAS-NS-3058	1965-09	txt
The Radiochemistry of Uranium	NAS-NS-3050	1962-03	txt
The Radiochemistry of the Rare Gases	NAS-NS-3025	1960-10	txt
The Radiochemistry of Protactinium	NAS-NS-3016	1959-12	txt
The Radiochemistry of Beryllium	NAS-NS-3013	1960-05	txt
The Radiochemistry of Thorium	NAS-NS-3004	1960-01	txt
Catalog of Nuclear Reactor Concepts: Part I. Homogeneous and Quasi-Homogeneous Reactors - Secition I. Particulate-Fueled Reactors	ANL-6892	1964-05	txt
Catalog of Nuclear Reactor Concepts: Part I. Homogeneous and Quasi-Homogeneous Reactors - Secition II. Reactors Fueled with Homogeneous Aqueous Solutions and Slurries	ANL-6909	1964-07	txt
Catalog of Nuclear Reactor Concepts: Part I. Homogeneous and Quasi-Homogeneous Reactors - Secition III. Reactors Fueled with Liquid Metals	ANL-7138	1966-01	txt
Catalog of Nuclear Reactor Concepts: Part I. Homogeneous and Quasi-Homogeneous Reactors - Secition V. Reactors Fueled with Uranium Hexafluoride, Gasses, or Plasmas	ANL-7180	1966-03	txt
Catalog of Nuclear Reactor Concepts: Part I. Homogeneous and Quasi-Homogeneous Reactors - Secition VI. Solid Homogeneous (Semihomogeneous) Reactors	ANL-7228	1966-06	txt
Hydroxides as Moderator Coolants in Power-Breeder-Reactors	BMI-746	1952-05	txt
Task I Final Report - Design Studies of Steam Generator for Molten Salt Reactors	ND-74-66	1975-01	txt
Nuclear Metallurgy, Volume 15, Symposium on Reprocessing of Nuclear Fuels	NSA-23-038023	1969-08	txt
Design Concepts for the Core Structure of a MOSEL (MOlten Salt ExperimentaL) Reactor	NSE-1965	1965-06	txt
Physical Properties Data Compilations Relevant to Energy Storage - IV. Molten Salts: Data on Additional Single and Multi-Component Salt Systems	NSRDS-NBS-61-p4	1988-08	txt
Aspects of Molten Fluorides as Heat Transfer Agents for Power Generation	P1152-2038	1979-02	txt
Fusion-Fission Energy Systems Evaluation	PNL-3116	1980-01	txt

---

New Piles Commitee

report	filename	date	ocr
Notes on Meeting of April 26, 1944	MUC-LAO-17	1944-04	txt
Notes on Meeting of April 28, 1944	MUC-LAO-18	1944-04	txt
Notes on Meeting of May 5, 1944	MUC-LAO-19	1944-05	txt
Notes on Meeting of May 10, 1944	MUC-LAO-20	1944-05	txt
Notes on Meeting of May 12, 1944	MUC-LAO-21	1944-05	txt
Notes on Meeting of July 6, 1944	MUC-LAO-30	1944-07	txt
Notes on Meeting of July 14, 1944	MUC-LAO-40	1944-07	txt
Notes on Meeting of July 26, 1944	MUC-LAO-41	1944-07	txt