A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
☆41Sep 13, 2021Updated 4 years ago
Alternatives and similar repositories for openmc_workshop
Users that are interested in openmc_workshop are comparing it to the libraries listed below
Sorting:
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆19Sep 13, 2021Updated 4 years ago
- Tools to translate between different CSG geometry types☆41May 28, 2025Updated 9 months ago
- Combines open source packages to produce an automated fusion specific neutronics workflow☆16May 31, 2022Updated 3 years ago
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆40Feb 11, 2026Updated 2 weeks ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆18Dec 11, 2025Updated 2 months ago
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10May 18, 2022Updated 3 years ago
- Collection of scripts for managing data for OpenMC☆39Dec 23, 2025Updated 2 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆53Dec 9, 2025Updated 2 months ago
- Collection of validation scripts, notebooks, results☆11Dec 23, 2025Updated 2 months ago
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Sep 5, 2024Updated last year
- OpenMC wrapped as a Moose App☆16May 1, 2023Updated 2 years ago
- Native plotting GUI for model design and verification☆65Feb 9, 2026Updated 2 weeks ago
- XSPlot - Neutron cross section plotter for isotopes☆14Jun 26, 2023Updated 2 years ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆123Feb 16, 2026Updated last week
- Create parametric 3D fusion reactor CAD models☆38Sep 23, 2021Updated 4 years ago
- ☆17Mar 26, 2024Updated last year
- Simulation of transmutation and decay in nuclear systems☆35Feb 21, 2026Updated last week
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆42Dec 11, 2024Updated last year
- ☆19Apr 16, 2022Updated 3 years ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Oct 20, 2022Updated 3 years ago
- Tool to estimate H retention in tokamak divertors☆10Oct 1, 2021Updated 4 years ago
- Sampling nuclear data and uncertainty☆56Updated this week
- 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 two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆43Dec 24, 2025Updated 2 months ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆175Updated this week
- Plugins and command extensions for Coreform Cubit☆18Jun 20, 2025Updated 8 months ago
- OpenMC Monte Carlo Code☆24Jan 31, 2025Updated last year
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆32Jan 29, 2026Updated last month
- Example Jupyter notebooks for OpenMC☆44Feb 28, 2025Updated last year
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆33Jan 27, 2026Updated last month
- Toolkit for reading and interacting with ENDF-6 formatted files☆42Jan 23, 2026Updated last month
- Workflow and Template Toolkit for Simulation (WATTS)☆33Jun 26, 2025Updated 8 months ago
- ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Ba…☆13Jul 30, 2017Updated 8 years ago
- A Python package for downloading h5 cross section files for use in OpenMC.☆15Jan 9, 2025Updated last year
- Automated V&V for fusion relevant CAD-based benchmarks☆23Jan 14, 2026Updated last month
- Create parametric 3D fusion reactor CAD and neutronics models☆92Sep 11, 2025Updated 5 months ago
- ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Ba…☆31Jun 4, 2024Updated last year
- Determine plasma flux functions for various plasma parameters and plasma configurations.☆13Mar 9, 2022Updated 3 years ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆66Jul 21, 2023Updated 2 years ago