Collection of validation scripts, notebooks, results
☆11Dec 23, 2025Updated 2 months ago
Alternatives and similar repositories for validation
Users that are interested in validation are comparing it to the libraries listed below
Sorting:
- Collection of scripts for managing data for OpenMC☆39Dec 23, 2025Updated 2 months ago
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10May 18, 2022Updated 3 years ago
- OpenMC Monte Carlo Code☆24Jan 31, 2025Updated last year
- Native plotting GUI for model design and verification☆65Feb 9, 2026Updated 2 weeks ago
- Simulation of transmutation and decay in nuclear systems☆35Feb 21, 2026Updated last week
- OpenMC wrapped as a Moose App☆16May 1, 2023Updated 2 years ago
- A depletion framework for OpenMC☆15Nov 27, 2017Updated 8 years ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Jun 25, 2024Updated last year
- Workflow and Template Toolkit for Simulation (WATTS)☆33Jun 26, 2025Updated 8 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆54Updated this week
- Format description for ACE nuclear data files☆22Apr 28, 2022Updated 3 years ago
- Collection of models for reactor physics benchmarks☆58Sep 17, 2025Updated 5 months ago
- XSPlot - Neutron cross section plotter for isotopes☆14Jun 26, 2023Updated 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
- 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
- Framework for REsearch in Nuclear ScIence and Engineering☆15Sep 8, 2021Updated 4 years ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆18Dec 11, 2025Updated 2 months ago
- List of open source projects related to OpenMC☆31Updated this week
- ENRICO: Exascale Nuclear Reactor Investigative COde☆66Jul 21, 2023Updated 2 years ago
- Sampling nuclear data and uncertainty☆56Updated this week
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆38Jul 3, 2025Updated 7 months ago
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆28May 19, 2021Updated 4 years ago
- JADE, a novel nuclear data libraries V&V tool☆34Feb 19, 2026Updated last week
- MC/DC: Monte Carlo Dynamic Code☆52Feb 20, 2026Updated last week
- Plugins and command extensions for Coreform Cubit☆18Jun 20, 2025Updated 8 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆43Dec 24, 2025Updated 2 months ago
- High-Fidelity Multiphysics☆128Feb 19, 2026Updated last week
- A set of radiation transport mini-applications used for performance optimization on HPC systems.☆29Aug 14, 2018Updated 7 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆53Dec 9, 2025Updated 2 months ago
- Example Jupyter notebooks for OpenMC☆43Feb 28, 2025Updated last year
- Python library for simple point-kernel photon shielding analyses☆15Jan 22, 2026Updated last month
- continuous energy monte carlo neutron transport in general geometries on GPUs☆46Jun 8, 2017Updated 8 years ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Oct 20, 2022Updated 3 years ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Jan 14, 2026Updated last month
- Stochastic Calculator Of Neutron transport Equation☆56Feb 18, 2026Updated last week
- CGMF nuclear fission fragment de-excitation statistical code☆28Mar 26, 2024Updated last year
- 3D visualizations for DAGMC & OpenMC☆14Jan 7, 2026Updated last month
- Script to help download, configure, install, and run the OpenMP offloading version of OpenMC☆10May 3, 2024Updated last year
- Simplified Stellarator CAD models.☆25Feb 20, 2026Updated last week