svalinn / pydagmcLinks
A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
☆16Updated last week
Alternatives and similar repositories for pydagmc
Users that are interested in pydagmc are comparing it to the libraries listed below
Sorting:
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated last week
- Accelerated Discretized Geometry☆17Updated last week
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- List of open source projects related to OpenMC☆26Updated last month
- Python ENDF Parser☆34Updated 11 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Convert OpenMC Geometry Components to CAD☆18Updated 7 months ago
- API for parsing and post-processing many MC simulations related files☆17Updated this week
- Computational inputs, reference outputs and experimental data for V&V systems☆13Updated 3 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆71Updated 3 weeks ago
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆29Updated this week
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆11Updated 2 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆43Updated last month
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated 10 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆47Updated this week
- JADE, a novel nuclear data libraries V&V tool☆31Updated last month
- open-source Sn software☆36Updated this week
- Native plotting GUI for model design and verification☆59Updated 5 months ago
- ☆31Updated 3 weeks ago
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆22Updated 2 months ago
- Tools to translate between different CSG geometry types☆39Updated last month
- Stochastic Calculator Of Neutron transport Equation☆45Updated last week
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆30Updated 2 weeks ago
- Workflow and Template Toolkit for Simulation (WATTS)☆32Updated 3 weeks ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆41Updated last year
- curated documents pertaining to early molten salt reactor research.☆22Updated last year
- Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis☆14Updated 4 years ago
- OpenMC Monte Carlo Code☆18Updated 5 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆38Updated last week
- Sampling nuclear data and uncertainty☆52Updated 3 weeks ago