openmsr / msre
detailed cad model of the msre
☆30Updated 4 months ago
Related projects: ⓘ
- Native plotting GUI for model design and verification☆45Updated last month
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆52Updated 3 months ago
- Stochastic Calculator Of Neutron transport Equation☆34Updated last week
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆12Updated 3 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆30Updated this week
- ENRICO: Exascale Nuclear Reactor Investigative COde☆61Updated last year
- Tools to translate between different CSG geometry types☆32Updated last year
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 3 weeks ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆53Updated last month
- List of open source projects related to OpenMC☆19Updated 3 weeks ago
- curated documents pertaining to early molten salt reactor research.☆20Updated 6 months ago
- Python ENDF Parser☆25Updated last month
- ☆61Updated 3 months ago
- Sampling nuclear data and uncertainty☆47Updated 2 weeks ago
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆20Updated 2 weeks ago
- Tool for converting MCNP input files to OpenMC classes/XML☆33Updated last month
- Monte Carlo Particle Lists☆28Updated 6 months ago
- A Python package for parsing FISPACT-II output☆25Updated 6 months ago
- JADE, a novel nuclear data libraries V&V tool☆23Updated last month
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆10Updated 2 weeks ago
- Thermal Scattering Library created with NJOY+NCrystal☆9Updated 2 years ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆118Updated 2 months ago
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆17Updated last year
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆35Updated 2 months ago
- ☆27Updated last year
- Direct Accelerated Geometry Monte Carlo Toolkit☆97Updated last month
- OpenMC Monte Carlo Code☆14Updated 3 weeks ago
- ☆16Updated last month
- Catalogs a plethora of reactor inputs for OpenMC☆18Updated 3 years ago