mit-crpg / openmc-workshopLinks
Contains slides and example problems for OpenMC workshops and presentations
☆24Updated 3 years ago
Alternatives and similar repositories for openmc-workshop
Users that are interested in openmc-workshop are comparing it to the libraries listed below
Sorting:
- List of open source projects related to OpenMC☆28Updated 5 months ago
- Native plotting GUI for model design and verification☆63Updated 2 weeks ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆164Updated last month
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆39Updated 3 weeks ago
- Sampling nuclear data and uncertainty☆52Updated 3 weeks ago
- Collection of models for reactor physics benchmarks☆56Updated last month
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- Example Jupyter notebooks for OpenMC☆39Updated 8 months ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- OpenMC Monte Carlo Code☆20Updated 9 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆49Updated last week
- Tools to translate between different CSG geometry types☆40Updated 5 months ago
- Catalogs a plethora of reactor inputs for OpenMC☆34Updated 8 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆80Updated this week
- Collection of scripts for managing data for OpenMC☆35Updated 9 months ago
- Parametric 3-D modeling toolset for stellarator fusion devices☆36Updated 2 weeks ago
- A method of characteristics code for nuclear reactor physics calculations.☆169Updated last year
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 3 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆116Updated 8 months ago
- API for parsing and post-processing many MC simulations related files☆17Updated last month
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆14Updated 5 months ago
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆32Updated 3 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆34Updated 4 months ago
- Accelerated Discretized Geometry☆18Updated last week
- Python ENDF Parser☆38Updated last week
- Convert OpenMC Geometry Components to CAD☆20Updated 11 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated last week
- ☆85Updated last year
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated 2 years ago