LLNL / fudge
For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
☆25Updated last month
Related projects ⓘ
Alternatives and complementary repositories for fudge
- Sampling nuclear data and uncertainty☆48Updated last month
- OpenMC Monte Carlo Code☆14Updated 2 months ago
- Workflow and Template Toolkit for Simulation (WATTS)☆24Updated 2 months ago
- List of open source projects related to OpenMC☆20Updated 2 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆57Updated 2 weeks ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆34Updated last week
- Tools to translate between different CSG geometry types☆35Updated last year
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆32Updated this week
- ☆17Updated 2 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆36Updated 2 weeks ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆12Updated 5 months ago
- Python ENDF Parser☆26Updated 3 months ago
- Stochastic Calculator Of Neutron transport Equation☆35Updated last month
- JADE, a novel nuclear data libraries V&V tool☆23Updated this week
- Collection of models for reactor physics benchmarks☆48Updated last month
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆52Updated 4 months ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆20Updated last month
- Collection of scripts for managing data for OpenMC☆27Updated 11 months ago
- A Python package for parsing FISPACT-II output☆25Updated 8 months ago
- Monte Carlo Particle Lists☆29Updated 8 months ago
- open-source Sn software☆21Updated this week
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆10Updated 2 years ago
- Simulation of transmutation and decay in nuclear systems☆27Updated 2 months ago
- ENDF/B pre-processing codes (PREPRO)☆16Updated last year
- XSPlot - Neutron cross section plotter for isotopes☆14Updated last year
- Native plotting GUI for model design and verification☆47Updated 2 weeks ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Some Monte Carlo tools☆45Updated 2 weeks ago
- ☆67Updated 5 months ago
- Catalogs a plethora of reactor inputs for OpenMC☆18Updated 3 years ago