ukaea / SpaceClaim_API_NeutronicsTools
Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis
☆13Updated 4 years ago
Alternatives and similar repositories for SpaceClaim_API_NeutronicsTools:
Users that are interested in SpaceClaim_API_NeutronicsTools are comparing it to the libraries listed below
- API for parsing and post-processing many MC simulations related files☆15Updated 3 weeks ago
- ☆21Updated 2 weeks ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆11Updated 11 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated this week
- List of open source projects related to OpenMC☆25Updated 7 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆40Updated 2 months ago
- Python ENDF Parser☆33Updated 8 months ago
- Convert OpenMC Geometry Components to CAD☆17Updated 5 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆67Updated last week
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆41Updated this week
- Accelerated Discretized Geometry☆13Updated this week
- ☆77Updated 10 months ago
- Tools to translate between different CSG geometry types☆37Updated last year
- JADE, a novel nuclear data libraries V&V tool☆26Updated this week
- Stochastic Calculator Of Neutron transport Equation☆42Updated last week
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆20Updated 6 months ago
- OpenMC Monte Carlo Code☆17Updated 2 months ago
- Thermal Scattering Library created with NJOY+NCrystal☆9Updated 2 years ago
- A Python package for parsing FISPACT-II output☆28Updated last week
- ENDF/B pre-processing codes (PREPRO)☆19Updated last year
- Sampling nuclear data and uncertainty☆51Updated last month
- Workflow and Template Toolkit for Simulation (WATTS)☆30Updated last week
- Monte Carlo Particle Lists☆30Updated this week
- Collection of scripts for managing data for OpenMC☆31Updated 3 months ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆29Updated 3 months ago
- Python package for reading, writing, verifying and translating ENDF-6 formatted files☆15Updated last month
- Easily access hydrogen transport properties☆15Updated 4 months ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆39Updated 3 weeks ago
- ENDF-6 data interface and nuclear data evaluation assist code☆16Updated last week