GEOUNED-org / GEOUNEDLinks
A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
☆84Updated last month
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☆30Updated 7 months ago
- Convert OpenMC Geometry Components to CAD☆20Updated last year
- API for parsing and post-processing many MC simulations related files☆17Updated this week
- Accelerated Discretized Geometry☆22Updated last week
- Python ENDF Parser☆39Updated 2 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆50Updated this week
- Tool for converting MCNP input files to OpenMC classes/XML☆52Updated last month
- Native plotting GUI for model design and verification☆64Updated last month
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated last week
- Tools to translate between different CSG geometry types☆40Updated 7 months ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆14Updated 8 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- Computational inputs, reference outputs and experimental data for V&V systems☆15Updated 4 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆18Updated last month
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆35Updated 6 months ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆173Updated last week
- Direct Accelerated Geometry Monte Carlo Toolkit☆120Updated 11 months ago
- OpenMC Monte Carlo Code☆24Updated 11 months ago
- ☆87Updated last year
- Meshing library for nuclear workflows☆69Updated 2 weeks ago
- Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis☆15Updated 4 years ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆40Updated 3 weeks ago
- Thermal Scattering Library created with NJOY+NCrystal☆10Updated 3 years ago
- Stochastic Calculator Of Neutron transport Equation☆55Updated this week
- Open-source Sn software☆54Updated this week
- NJOY for the 21st Century☆84Updated last year
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆24Updated last week
- ☆33Updated 6 months ago
- JADE, a novel nuclear data libraries V&V tool☆34Updated this week
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago