Python package for processing nuclear data distribution in ACE and ENDF format into HDF5 format for use in OpenMC. Adapted from the openmc data repo.
☆21Oct 20, 2026Updated last week
Alternatives and similar repositories for openmc_data
Users that are interested in openmc_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:
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆16May 6, 2025Updated last year
- Computational inputs, reference outputs and experimental data for V&V systems☆19Oct 13, 2026Updated 2 weeks ago
- Convert OpenMC Geometry Components to CAD☆21Nov 22, 2024Updated last year
- API for parsing and post-processing many MC simulations related files☆19Updated this week
- Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files☆65Updated this 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.
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆26Oct 15, 2026Updated 2 weeks ago
- Accelerated Discretized Geometry☆29Updated this week
- A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles☆14Oct 9, 2026Updated 2 weeks ago
- Open-source Sn software☆75Updated this week
- List of open source projects related to OpenMC☆42May 22, 2026Updated 5 months ago
- NeSST - Neutron Scattered Spectra Tool, primary and scattered fusion neutron spectroscopy analysis code☆13Sep 20, 2026Updated last month
- A plugin to convert CadQuery assemblies with tagged faces to a mesh☆16Jun 16, 2026Updated 4 months ago
- Simplified Stellarator CAD models.☆33Feb 20, 2026Updated 8 months ago
- A Python package for downloading h5 cross section files for use in OpenMC.☆17Jul 20, 2026Updated 3 months ago
- Deploy to Railway using AI coding agents - Free Credits Offer • AdUse Claude Code, Codex, OpenCode, and more. Autonomous software development now has the infrastructure to match with Railway.
- A Python-based Monte Carlo radiation transport code☆61Updated this week
- OpenMC Monte Carlo Code☆28Jan 31, 2025Updated last year
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆34Jul 17, 2026Updated 3 months ago
- Monte Carlo neutron source terms for SHINE's neutron generators☆15Apr 20, 2026Updated 6 months ago
- Meshing library for nuclear workflows☆83Updated this week
- Simulation of transmutation and decay in nuclear systems☆38Updated this week
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆101Sep 12, 2026Updated last month
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆203Sep 28, 2026Updated last month
- Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis☆15Mar 19, 2021Updated 5 years ago
- GPU virtual machines on DigitalOcean Gradient AI • AdGet to production fast with high-performance AMD and NVIDIA GPUs you can spin up in seconds. The definition of operational simplicity.
- Package for calculating the neutron energy, energy distribution and reactivity for neutrons from DT and DD fusion reactions☆13Updated this week
- Gxsview: Geometry and cross section viewer for calculating radiation transport☆14Feb 11, 2021Updated 5 years ago
- Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS☆137Oct 17, 2026Updated last week
- Stochastic Calculator Of Neutron transport Equation☆67Jul 28, 2026Updated 3 months ago
- Tool to transparently use shared libraries generated by Fortran within Python☆12Apr 28, 2026Updated 6 months ago
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Sep 5, 2024Updated 2 years ago
- A Python package for radioactive decay modelling that supports 1252 radionuclides, decay chains, branching, and metastable states.☆121Feb 10, 2025Updated last year
- Project repository for "An Open Source Nuclear Modeling Ecosystem to Support Fusion Pilot Plant Design" collaboration between MIT and ANL☆10Mar 5, 2026Updated 7 months ago
- ENDF/B pre-processing codes (PREPRO)☆23Aug 14, 2023Updated 3 years ago
- Deploy to Railway using AI coding agents - Free Credits Offer • AdUse Claude Code, Codex, OpenCode, and more. Autonomous software development now has the infrastructure to match with Railway.
- Parametric 3-D modeling toolset for stellarator fusion devices☆48Apr 23, 2026Updated 6 months ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆47Jun 25, 2024Updated 2 years ago
- The package for producing gamma spec from nuclide activities☆14Jan 16, 2025Updated last year
- Direct Accelerated Geometry Monte Carlo Toolkit☆135Sep 3, 2026Updated last month
- Python ENDF Parser☆46Oct 13, 2026Updated 2 weeks ago
- Tool for converting MCNP input files to OpenMC classes/XML☆64Sep 14, 2026Updated last month
- 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