mit-crpg / OpenMOCLinks
A method of characteristics code for nuclear reactor physics calculations.
☆167Updated 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☆114Updated 6 months ago
- Nuclear data processing with legacy NJOY☆115Updated 2 weeks ago
- NJOY for the 21st Century☆80Updated last year
- Stochastic Calculator Of Neutron transport Equation☆48Updated last week
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 4 months ago
- High-Fidelity Multiphysics☆119Updated 2 weeks ago
- Native plotting GUI for model design and verification☆60Updated last week
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆158Updated last week
- ENRICO: Exascale Nuclear Reactor Investigative COde☆66Updated 2 years ago
- Tools to translate between different CSG geometry types☆39Updated 3 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆39Updated 3 weeks ago
- PyNE: The Nuclear Engineering Toolkit☆300Updated last week
- Sampling nuclear data and uncertainty☆52Updated 2 weeks ago
- ☆84Updated last year
- Collection of models for reactor physics benchmarks☆54Updated 10 months ago
- List of open source projects related to OpenMC☆27Updated 3 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- Collection of scripts for managing data for OpenMC☆34Updated 7 months ago
- Catalogs a plethora of reactor inputs for OpenMC☆28Updated 6 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆44Updated 3 months ago
- Workflow and Template Toolkit for Simulation (WATTS)☆32Updated 2 months ago
- Python ENDF Parser☆35Updated 2 weeks ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆74Updated 2 months ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- open-source Sn software☆39Updated this week
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆59Updated last week
- Format description for ACE nuclear data files☆22Updated 3 years ago
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆20Updated last month
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆30Updated last month