mit-crpg / OpenMOCLinks
A method of characteristics code for nuclear reactor physics calculations.
☆169Updated last year
Alternatives and similar repositories for OpenMOC
Users that are interested in OpenMOC are comparing it to the libraries listed below
Sorting:
- Direct Accelerated Geometry Monte Carlo Toolkit☆116Updated 8 months ago
- Nuclear data processing with legacy NJOY☆117Updated 2 months ago
- NJOY for the 21st Century☆82Updated last year
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated last month
- Tools to translate between different CSG geometry types☆40Updated 5 months ago
- Stochastic Calculator Of Neutron transport Equation☆51Updated this week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆39Updated 3 weeks ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated 2 years ago
- High-Fidelity Multiphysics☆120Updated 3 weeks ago
- Collection of scripts for managing data for OpenMC☆35Updated 9 months ago
- Native plotting GUI for model design and verification☆63Updated last week
- PyNE: The Nuclear Engineering Toolkit☆304Updated last week
- List of open source projects related to OpenMC☆28Updated 5 months ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆164Updated 3 weeks ago
- Catalogs a plethora of reactor inputs for OpenMC☆34Updated 8 months ago
- Collection of models for reactor physics benchmarks☆56Updated last month
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 4 months ago
- Sampling nuclear data and uncertainty☆52Updated 3 weeks ago
- ☆85Updated last year
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- Tool for converting MCNP input files to OpenMC classes/XML☆47Updated last month
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- Format description for ACE nuclear data files☆22Updated 3 years ago
- Python ENDF Parser☆38Updated last week
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆80Updated last month
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆31Updated last week
- open-source Sn software☆48Updated last week
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆34Updated 3 months ago
- API for parsing and post-processing many MC simulations related files☆17Updated last month
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆32Updated 3 months ago