openmsr / msreLinks
detailed cad model of the msre
☆38Updated 7 months ago
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☆61Updated last month
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆160Updated last month
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 5 months ago
- High-Fidelity Multiphysics☆120Updated this week
- Tools to translate between different CSG geometry types☆39Updated 4 months ago
- Stochastic Calculator Of Neutron transport Equation☆51Updated last month
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- Python ENDF Parser☆37Updated last month
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 3 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 4 years ago
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆19Updated 2 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated last month
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 2 months ago
- List of open source projects related to OpenMC☆28Updated 3 months ago
- ☆32Updated 2 months ago
- JADE, a novel nuclear data libraries V&V tool☆32Updated last week
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆23Updated 4 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆79Updated 3 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆116Updated 7 months ago
- Sampling nuclear data and uncertainty☆52Updated last week
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆34Updated 2 months ago
- NJOY for the 21st Century☆80Updated last year
- ENRICO: Exascale Nuclear Reactor Investigative COde☆66Updated 2 years ago
- curated documents pertaining to early molten salt reactor research.☆22Updated last year
- Tool for converting MCNP input files to OpenMC classes/XML☆47Updated this week
- Convert OpenMC Geometry Components to CAD☆18Updated 10 months ago
- Format description for ACE nuclear data files☆22Updated 3 years ago
- API for parsing and post-processing many MC simulations related files☆17Updated last week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆39Updated 3 weeks ago