mctools / ncrystal
NCrystal : a library for thermal neutron transport in crystals and other materials
☆45Updated last week
Alternatives and similar repositories for ncrystal:
Users that are interested in ncrystal are comparing it to the libraries listed below
- primary knock-on atom (PKA) spectrum evaluator☆17Updated 3 months ago
- ENDF/B pre-processing codes (PREPRO)☆19Updated last year
- Python ENDF Parser☆33Updated 9 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated 2 weeks ago
- Tool for converting MCNP input files to OpenMC classes/XML☆40Updated 2 months ago
- NJOY for the 21st Century☆78Updated last year
- Thermal Scattering Library created with NJOY+NCrystal☆9Updated 3 years ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated this week
- ☆22Updated this week
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆69Updated 3 weeks ago
- List of open source projects related to OpenMC☆25Updated 8 months ago
- open-source Sn software☆33Updated last week
- Stochastic Calculator Of Neutron transport Equation☆43Updated 3 weeks ago
- Sampling nuclear data and uncertainty☆51Updated this week
- ☆77Updated 11 months ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆29Updated 2 weeks ago
- Format description for ACE nuclear data files☆21Updated 3 years ago
- Monte Carlo Particle Lists☆30Updated this week
- API for parsing and post-processing many MC simulations related files☆15Updated 2 weeks ago
- Workflow and Template Toolkit for Simulation (WATTS)☆30Updated this week
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆43Updated this week
- Papillon Nuclear Data Library☆16Updated 8 months ago
- Tools to translate between different CSG geometry types☆37Updated last year
- OpenMC Monte Carlo Code☆17Updated 3 months ago
- Convert OpenMC Geometry Components to CAD☆17Updated 5 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆57Updated 3 weeks ago
- Nuclear data processing with legacy NJOY☆106Updated 3 weeks ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆32Updated this week
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆40Updated 10 months ago
- ENDF-6 data interface and nuclear data evaluation assist code☆16Updated last week