lanl / mcnptools
☆76Updated 9 months ago
Alternatives and similar repositories for mcnptools:
Users that are interested in mcnptools are comparing it to the libraries listed below
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆60Updated last week
- Tools to translate between different CSG geometry types☆36Updated last year
- Tool for converting MCNP input files to OpenMC classes/XML☆37Updated 2 weeks ago
- Native plotting GUI for model design and verification☆55Updated last month
- Thermal Scattering Library created with NJOY+NCrystal☆9Updated 2 years ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆37Updated this week
- NJOY for the 21st Century☆78Updated last year
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆109Updated 2 weeks ago
- Sampling nuclear data and uncertainty☆50Updated last month
- Toolkit for reading and interacting with ENDF-6 formatted files☆37Updated last week
- Nuclear data processing with legacy NJOY☆103Updated last month
- Python ENDF Parser☆28Updated 7 months ago
- List of open source projects related to OpenMC☆24Updated 6 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆55Updated 2 weeks ago
- Monte Carlo Particle Lists☆30Updated last year
- A Python package for parsing FISPACT-II output☆26Updated last year
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆33Updated 2 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆14Updated last month
- OpenMC Monte Carlo Code☆17Updated last month
- Some Monte Carlo tools☆47Updated 2 months ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆28Updated last month
- Convert OpenMC Geometry Components to CAD☆16Updated 3 months ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆136Updated this week
- JADE, a novel nuclear data libraries V&V tool☆25Updated this week
- Stochastic Calculator Of Neutron transport Equation☆40Updated last month
- ENDF/B pre-processing codes (PREPRO)☆17Updated last year
- Example Jupyter notebooks for OpenMC☆35Updated this week
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 6 months ago
- Contains slides and example problems for OpenMC workshops and presentations☆23Updated 2 years ago