Tool for converting MCNP input files to OpenMC classes/XML
☆64Sep 14, 2026Updated 3 weeks ago
Alternatives and similar repositories for openmc_mcnp_adapter
Users that are interested in openmc_mcnp_adapter are comparing it to the libraries listed below. We may earn a commission when you buy through links labeled 'Ad' on this page.
Sorting:
- List of open source projects related to OpenMC☆42May 22, 2026Updated 4 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆12Oct 20, 2022Updated 3 years ago
- Native plotting GUI for model design and verification☆74Sep 3, 2026Updated last month
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆101Sep 12, 2026Updated 3 weeks ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆66Sep 29, 2026Updated last week
- Serverless GPU API endpoints on Runpod - Get Bonus Credits • AdSkip the infrastructure headaches. Auto-scaling, pay-as-you-go, no-ops approach lets you focus on innovating your application.
- Toolkit for reading and interacting with ENDF-6 formatted files☆42Sep 17, 2026Updated 3 weeks ago
- A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles☆13Feb 10, 2026Updated 8 months ago
- Convert OpenMC Geometry Components to CAD☆21Nov 22, 2024Updated last year
- 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
- Example Jupyter notebooks for OpenMC☆51Feb 28, 2025Updated last year
- A tool for making reproducible materials and standardizing use across several neutronics codes☆28Aug 27, 2026Updated last month
- Sampling nuclear data and uncertainty☆62May 29, 2026Updated 4 months ago
- JADE, a novel nuclear data libraries V&V tool☆42Oct 1, 2026Updated last week
- Workflow and Template Toolkit for Simulation (WATTS)☆39Jul 24, 2026Updated 2 months ago
- GPUs on demand by Runpod - Special Offer Available • AdRun AI, ML, and HPC workloads on powerful cloud GPUs—without limits or wasted spend. Deploy GPUs in under a minute and pay by the second.
- Automated V&V for fusion relevant CAD-based benchmarks☆25Apr 8, 2026Updated 6 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆18Dec 11, 2025Updated 9 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Sep 13, 2021Updated 5 years ago
- ENDF/B pre-processing codes (PREPRO)☆23Aug 14, 2023Updated 3 years ago
- Tools to translate between different CSG geometry types☆44May 28, 2025Updated last year
- OpenMC Monte Carlo Code☆28Jan 31, 2025Updated last year
- Monte Carlo neutron source terms for SHINE's neutron generators☆15Apr 20, 2026Updated 5 months ago
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆46Jun 24, 2026Updated 3 months ago
- Collection of models for reactor physics benchmarks☆69Sep 17, 2025Updated last year
- 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.
- Python ENDF Parser☆46Sep 3, 2026Updated last month
- Simulation of transmutation and decay in nuclear systems☆38Updated this week
- Toolkit for working with ACE-formatted data files☆34Sep 14, 2026Updated 3 weeks ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆36Sep 30, 2026Updated last week
- Repository for running SINBAD benchmarks with OpenMC and UQ☆12May 18, 2022Updated 4 years ago
- ☆97May 30, 2024Updated 2 years ago
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆26Jul 30, 2026Updated 2 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆49Dec 24, 2025Updated 9 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆133Sep 3, 2026Updated last month
- Serverless GPU API endpoints on Runpod - Get Bonus Credits • AdSkip the infrastructure headaches. Auto-scaling, pay-as-you-go, no-ops approach lets you focus on innovating your application.
- Computational inputs, reference outputs and experimental data for V&V systems☆18Oct 1, 2026Updated last week
- continuous energy monte carlo neutron transport in general geometries on GPUs☆53Jun 8, 2017Updated 9 years ago
- Contains slides and example problems for OpenMC workshops and presentations☆28Jun 13, 2022Updated 4 years ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆16May 6, 2025Updated last year
- API for parsing and post-processing many MC simulations related files☆19Oct 1, 2026Updated last week
- NCrystal : a library for thermal neutron transport in crystals and other materials☆55Oct 2, 2026Updated last week
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆201Sep 28, 2026Updated last week