Catalogs a plethora of reactor inputs for OpenMC
☆35Feb 28, 2025Updated last year
Alternatives and similar repositories for openmc-reactor-examples
Users that are interested in openmc-reactor-examples are comparing it to the libraries listed below. We may earn a commission when you buy through links labeled 'Ad' on this page.
Sorting:
- OpenMC Workshop for Canadian Nuclear Laboratories☆12Mar 17, 2017Updated 9 years ago
- Contains slides and example problems for OpenMC workshops and presentations☆26Jun 13, 2022Updated 3 years ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆43Dec 24, 2025Updated 3 months ago
- Simulate PWR,CANDU and VVER reactor (Assembly Model) using OpenMC https://openmc.readthedocs.io/en/stable/☆14Nov 29, 2019Updated 6 years ago
- List of open source projects related to OpenMC☆34Feb 24, 2026Updated last month
- A depletion framework for OpenMC☆15Nov 27, 2017Updated 8 years ago
- Convert OpenMC Geometry Components to CAD☆20Nov 22, 2024Updated last year
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Oct 20, 2022Updated 3 years ago
- Native plotting GUI for model design and verification☆65Mar 7, 2026Updated 2 weeks ago
- Example Jupyter notebooks for OpenMC☆43Feb 28, 2025Updated last year
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆39Jul 3, 2025Updated 8 months ago
- High-Fidelity Multiphysics☆132Mar 18, 2026Updated last week
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆62Sep 30, 2025Updated 5 months ago
- A method of characteristics code for nuclear reactor physics calculations.☆180Jul 19, 2024Updated last year
- curated documents pertaining to early molten salt reactor research.☆27Mar 7, 2024Updated 2 years ago
- A curated list of open source projects used in nuclear science and engineering☆457Feb 4, 2026Updated last month
- Three-Dimensional Discrete Ordinates Neutron, Photon, Electron and Positron Transport Code☆12Feb 26, 2022Updated 4 years ago
- Repository of FEMFFUSION: a finite element code for nuclear reactor modelling. FEMFFUSION is an open source C++ neutronic code to solve t…☆17Feb 27, 2026Updated 3 weeks ago
- OpenMC wrapped as a Moose App☆16May 1, 2023Updated 2 years ago
- Sampling nuclear data and uncertainty☆57Mar 17, 2026Updated last week
- OpenMC Monte Carlo Code☆986Mar 17, 2026Updated last week
- NJOY for the 21st Century☆86Jan 22, 2024Updated 2 years ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Sep 13, 2021Updated 4 years ago
- ENDF/B pre-processing codes (PREPRO)☆22Aug 14, 2023Updated 2 years ago
- The sciantix-official repository contains the SCIANTIX code for fission gas behaviour, together with the validation database and regressi…☆13Updated this week
- Tools to translate between different CSG geometry types☆41May 28, 2025Updated 9 months ago
- Nuclear data processing with legacy NJOY☆127Updated this week
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10May 18, 2022Updated 3 years ago
- MC/DC: Monte Carlo Dynamic Code☆52Mar 5, 2026Updated 2 weeks ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆88Feb 20, 2026Updated last month
- detailed cad model of the msre☆43Oct 29, 2025Updated 4 months ago
- Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API☆11Oct 11, 2023Updated 2 years ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆18Dec 11, 2025Updated 3 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆57Dec 9, 2025Updated 3 months ago
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆44Dec 11, 2024Updated last year
- Collection of validation scripts, notebooks, results☆11Dec 23, 2025Updated 3 months ago
- Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files☆53Mar 16, 2026Updated last week
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆19Sep 13, 2021Updated 4 years ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆177Mar 6, 2026Updated 2 weeks ago