pshriwise / xdgLinks
Accelerated Discretized Geometry
☆18Updated this week
Alternatives and similar repositories for xdg
Users that are interested in xdg are comparing it to the libraries listed below
Sorting:
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 2 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated 3 weeks ago
- List of open source projects related to OpenMC☆27Updated 3 months ago
- Python ENDF Parser☆36Updated last month
- Computational inputs, reference outputs and experimental data for V&V systems☆14Updated last week
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- Convert OpenMC Geometry Components to CAD☆18Updated 10 months ago
- API for parsing and post-processing many MC simulations related files☆17Updated this week
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 4 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆46Updated this week
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆77Updated 2 months ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆13Updated 4 months ago
- ☆32Updated 2 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆22Updated 4 months ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆30Updated last month
- Native plotting GUI for model design and verification☆60Updated last month
- JADE, a novel nuclear data libraries V&V tool☆32Updated last week
- open-source Sn software☆42Updated last week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆39Updated 2 weeks ago
- Stochastic Calculator Of Neutron transport Equation☆51Updated 3 weeks ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆32Updated 2 months ago
- Tools to translate between different CSG geometry types☆39Updated 3 months ago
- OpenMC Monte Carlo Code☆18Updated 7 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 5 months ago
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆31Updated last month
- XSPlot - Neutron cross section plotter for isotopes☆14Updated 2 years ago
- Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis☆14Updated 4 years ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆159Updated last month