makeclean / csg2csgLinks
Tools to translate between different CSG geometry types
☆40Updated 8 months ago
Alternatives and similar repositories for csg2csg
Users that are interested in csg2csg are comparing it to the libraries listed below
Sorting:
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- List of open source projects related to OpenMC☆31Updated 8 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆53Updated last month
- Python ENDF Parser☆39Updated last week
- Native plotting GUI for model design and verification☆64Updated last week
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 3 weeks ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 4 months ago
- API for parsing and post-processing many MC simulations related files☆17Updated last week
- Stochastic Calculator Of Neutron transport Equation☆55Updated 2 weeks ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆32Updated last week
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆85Updated 2 months ago
- Accelerated Discretized Geometry☆23Updated 3 weeks ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆120Updated 11 months ago
- NJOY for the 21st Century☆84Updated 2 years ago
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 7 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆52Updated this week
- Convert OpenMC Geometry Components to CAD☆20Updated last year
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆41Updated last month
- ☆87Updated last year
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆18Updated last month
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆175Updated this week
- Nuclear data processing with legacy NJOY☆123Updated 2 weeks ago
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆24Updated 3 weeks ago
- OpenMC Monte Carlo Code☆24Updated last year
- Catalogs a plethora of reactor inputs for OpenMC☆35Updated 11 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 3 years ago
- ☆33Updated 6 months ago
- JADE, a novel nuclear data libraries V&V tool☆34Updated 3 weeks ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆14Updated 9 months ago