toshihikokawano / DeCELinks
ENDF-6 data interface and nuclear data evaluation assist code
☆16Updated 6 months ago
Alternatives and similar repositories for DeCE
Users that are interested in DeCE are comparing it to the libraries listed below
Sorting:
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated last week
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 3 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆17Updated 2 weeks ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆31Updated last week
- Python ENDF Parser☆38Updated last week
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago
- Accelerated Discretized Geometry☆18Updated this week
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 3 years ago
- NJOY for the 21st Century☆83Updated last year
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- Sampling nuclear data and uncertainty☆52Updated 3 weeks ago
- List of open source projects related to OpenMC☆28Updated 5 months ago
- open-source Sn software☆48Updated this week
- Nuclear data processing with legacy NJOY☆117Updated 2 months ago
- JADE, a novel nuclear data libraries V&V tool☆33Updated last week
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆19Updated 4 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆49Updated last week
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆32Updated 3 months ago
- ☆32Updated 3 months ago
- Tools to translate between different CSG geometry types☆40Updated 5 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated last month
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- Format description for ACE nuclear data files☆22Updated 3 years ago
- OpenMC Monte Carlo Code☆22Updated 9 months ago
- Toolkit for working with ACE-formatted data files☆30Updated 2 months ago
- Stochastic Calculator Of Neutron transport Equation☆51Updated last week
- Native plotting GUI for model design and verification☆64Updated 2 weeks ago
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated last year
- Convert OpenMC Geometry Components to CAD☆20Updated 11 months ago