openmsr / msreLinks
detailed cad model of the msre
☆38Updated last week
Alternatives and similar repositories for msre
Users that are interested in msre are comparing it to the libraries listed below
Sorting:
- Native plotting GUI for model design and verification☆62Updated this week
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 3 weeks ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated last month
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆40Updated 4 years ago
- Tools to translate between different CSG geometry types☆39Updated 4 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆116Updated 8 months ago
- List of open source projects related to OpenMC☆28Updated 4 months ago
- Stochastic Calculator Of Neutron transport Equation☆51Updated last week
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 3 months ago
- High-Fidelity Multiphysics☆120Updated last week
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆24Updated 5 months ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated 2 years ago
- Python ENDF Parser☆38Updated 2 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆79Updated 2 weeks ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 3 years ago
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 3 months ago
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆32Updated 2 months ago
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆20Updated 3 months ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆163Updated 2 weeks ago
- A method of characteristics code for nuclear reactor physics calculations.☆169Updated last year
- Catalogs a plethora of reactor inputs for OpenMC☆33Updated 7 months ago
- NJOY for the 21st Century☆82Updated last year
- ☆32Updated 3 months ago
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated last year
- Sampling nuclear data and uncertainty☆52Updated 2 weeks ago
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆35Updated 3 months ago
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆62Updated this week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆39Updated 2 weeks ago