LLNL / fudgeLinks
For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
☆30Updated last month
Alternatives and similar repositories for fudge
Users that are interested in fudge are comparing it to the libraries listed below
Sorting:
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated last month
- Python ENDF Parser☆35Updated 2 weeks ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- List of open source projects related to OpenMC☆27Updated 3 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated this week
- Tools to translate between different CSG geometry types☆39Updated 3 months ago
- Sampling nuclear data and uncertainty☆52Updated 2 weeks ago
- Accelerated Discretized Geometry☆18Updated 3 weeks ago
- JADE, a novel nuclear data libraries V&V tool☆32Updated 2 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- Stochastic Calculator Of Neutron transport Equation☆50Updated last week
- Tool for converting MCNP input files to OpenMC classes/XML☆44Updated 3 months ago
- Native plotting GUI for model design and verification☆60Updated last week
- API for parsing and post-processing many MC simulations related files☆17Updated 3 weeks ago
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆19Updated 3 years ago
- ENDF-6 data interface and nuclear data evaluation assist code☆16Updated 4 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated last week
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 4 months ago
- Collection of scripts for managing data for OpenMC☆34Updated 7 months ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆12Updated 3 months ago
- NJOY for the 21st Century☆80Updated last year
- open-source Sn software☆39Updated this week
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆31Updated last month
- Workflow and Template Toolkit for Simulation (WATTS)☆32Updated 2 months ago
- Nuclear data processing with legacy NJOY☆117Updated this week
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated last week
- XSPlot - Neutron cross section plotter for isotopes☆14Updated 2 years ago
- OpenMC Monte Carlo Code☆18Updated 7 months ago
- ☆32Updated last month
- Convert OpenMC Geometry Components to CAD☆18Updated 9 months ago