llnl / fudgeLinks
For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
☆32Updated 3 months ago
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 2 weeks ago
- Python ENDF Parser☆39Updated this week
- Sampling nuclear data and uncertainty☆55Updated 3 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 3 years ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- Tools to translate between different CSG geometry types☆40Updated 8 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆18Updated last month
- List of open source projects related to OpenMC☆30Updated 8 months ago
- Accelerated Discretized Geometry☆23Updated 2 weeks ago
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆19Updated 4 years ago
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆52Updated last month
- Toolkit for reading and interacting with ENDF-6 formatted files☆41Updated last week
- Stochastic Calculator Of Neutron transport Equation☆55Updated last week
- NJOY for the 21st Century☆84Updated 2 years ago
- JADE, a novel nuclear data libraries V&V tool☆34Updated 2 weeks ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆51Updated this week
- API for parsing and post-processing many MC simulations related files☆17Updated last week
- Native plotting GUI for model design and verification☆64Updated last week
- ENDF-6 data interface and nuclear data evaluation assist code☆17Updated 9 months ago
- Open-source Sn software☆54Updated this week
- Collection of scripts for managing data for OpenMC☆38Updated last month
- ENDF/B pre-processing codes (PREPRO)☆22Updated 2 years ago
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 7 months ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆14Updated 8 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆120Updated 11 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 4 months ago
- OpenMC Monte Carlo Code☆24Updated last year
- Nuclear data processing with legacy NJOY☆123Updated last week
- Toolkit for working with ACE-formatted data files☆31Updated 3 weeks ago