njoy / NJOY2016Links
Nuclear data processing with legacy NJOY
☆123Updated 3 weeks ago
Alternatives and similar repositories for NJOY2016
Users that are interested in NJOY2016 are comparing it to the libraries listed below
Sorting:
- NJOY for the 21st Century☆84Updated 2 years ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆42Updated last month
- Direct Accelerated Geometry Monte Carlo Toolkit☆122Updated 11 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆62Updated 4 months ago
- List of open source projects related to OpenMC☆31Updated 8 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆53Updated 2 months ago
- Stochastic Calculator Of Neutron transport Equation☆56Updated 3 weeks ago
- Tools to translate between different CSG geometry types☆40Updated 8 months ago
- Native plotting GUI for model design and verification☆65Updated 2 weeks ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- Python ENDF Parser☆39Updated 2 weeks ago
- ☆87Updated last year
- Toolkit for reading and interacting with ENDF-6 formatted files☆41Updated 2 weeks ago
- A method of characteristics code for nuclear reactor physics calculations.☆179Updated last year
- API for parsing and post-processing many MC simulations related files☆17Updated this week
- Catalogs a plethora of reactor inputs for OpenMC☆35Updated 11 months ago
- ☆33Updated 6 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆52Updated last week
- Convert OpenMC Geometry Components to CAD☆20Updated last year
- Toolkit for working with ACE-formatted data files☆31Updated this week
- Format description for ACE nuclear data files☆22Updated 3 years ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 3 weeks ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆66Updated 2 years ago
- JADE, a novel nuclear data libraries V&V tool☆34Updated 3 weeks ago
- Open-source Sn software☆58Updated this week
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆85Updated 2 months ago
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆42Updated last year
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆18Updated last month
- Three-Dimensional Discrete Ordinates Neutron, Photon, Electron and Positron Transport Code☆12Updated 3 years ago
- Sampling nuclear data and uncertainty☆55Updated 4 months ago