GEOUNED-org / GEOUNEDLinks
A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
☆79Updated last week
Alternatives and similar repositories for GEOUNED
Users that are interested in GEOUNED are comparing it to the libraries listed below
Sorting:
- List of open source projects related to OpenMC☆28Updated 4 months ago
- API for parsing and post-processing many MC simulations related files☆17Updated 3 weeks ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- Tool for converting MCNP input files to OpenMC classes/XML☆47Updated 2 weeks ago
- Convert OpenMC Geometry Components to CAD☆20Updated 10 months ago
- Accelerated Discretized Geometry☆18Updated last week
- Native plotting GUI for model design and verification☆62Updated last month
- Python ENDF Parser☆38Updated last month
- Meshing library for nuclear workflows☆51Updated 3 weeks ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated last month
- Computational inputs, reference outputs and experimental data for V&V systems☆15Updated 3 weeks ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 2 months ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆14Updated 5 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆34Updated 3 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆116Updated 7 months ago
- Tools to translate between different CSG geometry types☆39Updated 4 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆39Updated this week
- open-source Sn software☆44Updated this week
- Stochastic Calculator Of Neutron transport Equation☆51Updated last month
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 4 years ago
- ☆85Updated last year
- NJOY for the 21st Century☆81Updated last year
- OpenMC Monte Carlo Code☆18Updated 8 months ago
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago
- Nuclear data processing with legacy NJOY☆117Updated last month
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆23Updated 4 months ago
- ☆32Updated 2 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆32Updated 2 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated last week