OpenMC Monte Carlo Code
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Updated
Sep 7, 2024 - Python
OpenMC Monte Carlo Code
☢️ Simulate nuclear isotopic chemistry for element creation.
Main yt repository
A repository to hold transition scenarios with Cyclus.
List of open source projects related to OpenMC
MC/DC: Monte Carlo Dynamic Code
The sciantix-official repository contains the SCIANTIX code for inert gas behaviour, together with the validation database and regression files.
Python Framework for data-driven model Order Reduction of multi-physiCs problEms
Papillon Nuclear Data Library
Tools to work with MCNP models and results
A curated list of open source projects used in nuclear science and engineering
Holds the research group website.
Tool for converting MCNP input files to OpenMC classes/XML
Energy-dependent neutron transport Monte Carlo implemented in Rust.
An open source utility to convert various publicly available macroscopic nuclear cross section formats
Python package for generating a core, time-dependent geometry for reactor analyses with FRENETIC and FreeFEM++ codes.
THOR is a radiation transport code for unstructured meshes.
The main whatisnuclear.com website
An attempt at developing an optimized control rod design for a nuclear reactor using a genetic algorithm and perturbation theory of the simple neutron diffusion equation model.
A set of MATLAB scripts that runs SRIM2013 natively within MATLAB for displacement-per-atom (DPA) calculations
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