JADE-V-V / JADELinks
JADE, a novel nuclear data libraries V&V tool
☆29Updated 3 weeks ago
Alternatives and similar repositories for JADE
Users that are interested in JADE are comparing it to the libraries listed below
Sorting:
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 2 weeks ago
- API for parsing and post-processing many MC simulations related files☆17Updated last week
- Computational inputs, reference outputs and experimental data for V&V systems☆13Updated 2 months ago
- Python ENDF Parser☆33Updated 10 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆42Updated last month
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆47Updated 2 weeks ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Accelerated Discretized Geometry☆17Updated last week
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated last month
- List of open source projects related to OpenMC☆26Updated 3 weeks ago
- Thermal Scattering Library created with NJOY+NCrystal☆9Updated 3 years ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆70Updated this week
- Convert OpenMC Geometry Components to CAD☆18Updated 7 months ago
- Python package for reading, writing, verifying and translating ENDF-6 formatted files☆16Updated 2 weeks ago
- Monte Carlo Particle Lists☆32Updated last week
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆29Updated 2 weeks ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆41Updated 2 weeks ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆11Updated last month
- ENDF/B pre-processing codes (PREPRO)☆19Updated last year
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆22Updated last month
- A Python package for parsing FISPACT-II output☆29Updated last month
- ☆79Updated last year
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆58Updated 2 months ago
- MCNP6 Syntax highlighting and code snippets for VSCode. Written primarily for MCNP6.x input decks.☆13Updated 11 months ago
- Native plotting GUI for model design and verification☆59Updated 5 months ago
- Tools to translate between different CSG geometry types☆38Updated 3 weeks ago
- Stochastic Calculator Of Neutron transport Equation☆44Updated 2 weeks ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆24Updated 8 months ago
- Sampling nuclear data and uncertainty☆51Updated last week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆36Updated 3 months ago