Collection of scripts for managing data for OpenMC
☆40Mar 3, 2026Updated 3 months ago
Alternatives and similar repositories for data
Users that are interested in data are comparing it to the libraries listed below. We may earn a commission when you buy through links labeled 'Ad' on this page.
Sorting:
- Collection of validation scripts, notebooks, results☆11Dec 23, 2025Updated 5 months ago
- Native plotting GUI for model design and verification☆72Mar 7, 2026Updated 3 months ago
- OpenMC wrapped as a Moose App☆16May 1, 2023Updated 3 years ago
- Repository for running SINBAD benchmarks with OpenMC and UQ☆12May 18, 2022Updated 4 years ago
- Tools to translate between different CSG geometry types☆44May 28, 2025Updated last year
- Proton VPN Special Offer - Get 70% off • AdSpecial partner offer. Trusted by over 100 million users worldwide. Tested, Approved and Recommended by Experts.
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆42Sep 13, 2021Updated 4 years ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆62Sep 30, 2025Updated 8 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆128Feb 16, 2026Updated 3 months ago
- The Advanced Dimensional Depletion for Engineering of Reactors (ADDER) Software☆20May 20, 2026Updated 2 weeks ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆45Dec 24, 2025Updated 5 months ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆16May 6, 2025Updated last year
- OpenMC中文教程 ( 如何编译、安装、使用OpenMC教程 )☆47Jul 12, 2021Updated 4 years ago
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆30May 19, 2021Updated 5 years ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆44Jun 25, 2024Updated last year
- Deploy on Railway without the complexity - Free Credits Offer • AdConnect your repo and Railway handles the rest with instant previews. Quickly provision container image services, databases, and storage volumes.
- Format description for ACE nuclear data files☆23Apr 28, 2022Updated 4 years ago
- A curated list of open source projects used in nuclear science and engineering☆474Feb 4, 2026Updated 4 months ago
- Simulation of transmutation and decay in nuclear systems☆36Updated this week
- Collection of models for reactor physics benchmarks☆63Sep 17, 2025Updated 8 months ago
- Plugins and command extensions for Coreform Cubit☆18Jun 20, 2025Updated 11 months ago
- High-Fidelity Multiphysics☆140Updated this week
- ENRICO: Exascale Nuclear Reactor Investigative COde☆68Jul 21, 2023Updated 2 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…☆46Dec 11, 2024Updated last year
- Sampling nuclear data and uncertainty☆59May 29, 2026Updated last week
- Wordpress hosting with auto-scaling - Free Trial Offer • AdFully Managed hosting for WordPress and WooCommerce businesses that need reliable, auto-scalable performance. Cloudways SafeUpdates now available.
- JADE, a novel nuclear data libraries V&V tool☆38Updated this week
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆189Updated this week
- OpenMC Monte Carlo Code☆27Jan 31, 2025Updated last year
- Workflow and Template Toolkit for Simulation (WATTS)☆38Jun 26, 2025Updated 11 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆40Jul 3, 2025Updated 11 months ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆34May 22, 2026Updated 2 weeks ago
- List of open source projects related to OpenMC☆38May 22, 2026Updated 2 weeks ago
- A set of radiation transport mini-applications used for performance optimization on HPC systems.☆29Aug 14, 2018Updated 7 years ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆64Updated this week
- AI Agents on DigitalOcean Gradient AI Platform • AdBuild production-ready AI agents using customizable tools or access multiple LLMs through a single endpoint. Create custom knowledge bases or connect external data.
- Online reprocessing for molten salt reactors☆24Apr 24, 2025Updated last year
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆42Updated this week
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆20Sep 13, 2021Updated 4 years ago
- Automated V&V for fusion relevant CAD-based benchmarks☆24Apr 8, 2026Updated 2 months ago
- A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles☆13Feb 10, 2026Updated 3 months ago
- Example Jupyter notebooks for OpenMC☆46Feb 28, 2025Updated last year
- 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