njoy / ACEtkLinks
Toolkit for working with ACE-formatted data files
☆30Updated 3 months ago
Alternatives and similar repositories for ACEtk
Users that are interested in ACEtk are comparing it to the libraries listed below
Sorting:
- ENDF/B pre-processing codes (PREPRO)☆21Updated 2 years ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆41Updated last month
- Python ENDF Parser☆39Updated 2 months ago
- A code package to produce ACE-formatted files for MCNP calculations.☆12Updated 6 months ago
- NJOY for the 21st Century☆84Updated last year
- Sampling nuclear data and uncertainty☆54Updated 2 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆52Updated 3 weeks 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
- Format description for ACE nuclear data files☆22Updated 3 years ago
- Nuclear data processing with legacy NJOY☆122Updated 2 weeks ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆118Updated 10 months ago
- Papillon Nuclear Data Library☆18Updated 5 months ago
- Tools to translate between different CSG geometry types☆40Updated 7 months ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated last week
- JADE, a novel nuclear data libraries V&V tool☆34Updated last week
- Native plotting GUI for model design and verification☆64Updated last month
- List of open source projects related to OpenMC☆30Updated 7 months ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆32Updated 2 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆83Updated 3 weeks ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- NCrystal : a library for thermal neutron transport in crystals and other materials☆45Updated 2 weeks ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 3 months ago
- Collection of scripts for managing data for OpenMC☆38Updated last week
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆18Updated 2 weeks ago
- Open-source Sn software☆53Updated this week
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 3 years ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- API for parsing and post-processing many MC simulations related files☆17Updated last week
- ENRICO: Exascale Nuclear Reactor Investigative COde☆66Updated 2 years ago