mit-crpg / benchmarksLinks
Collection of models for reactor physics benchmarks
☆52Updated 8 months ago
Alternatives and similar repositories for benchmarks
Users that are interested in benchmarks are comparing it to the libraries listed below
Sorting:
- Collection of scripts for managing data for OpenMC☆33Updated 4 months ago
- open-source Sn software☆34Updated this week
- Stochastic Calculator Of Neutron transport Equation☆43Updated 3 weeks ago
- List of open source projects related to OpenMC☆26Updated last week
- OpenMC Monte Carlo Code☆18Updated 4 months ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated this week
- Computational inputs, reference outputs and experimental data for V&V systems☆13Updated last month
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- Workflow and Template Toolkit for Simulation (WATTS)☆30Updated last month
- Native plotting GUI for model design and verification☆58Updated 4 months ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆40Updated 11 months ago
- Format description for ACE nuclear data files☆21Updated 3 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆42Updated 2 weeks ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆34Updated 2 months ago
- Sampling nuclear data and uncertainty☆51Updated last month
- JADE, a novel nuclear data libraries V&V tool☆29Updated this week
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆32Updated 2 weeks ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated 3 weeks ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Convert OpenMC Geometry Components to CAD☆18Updated 6 months ago
- Tools to translate between different CSG geometry types☆37Updated last week
- Python ENDF Parser☆33Updated 10 months ago
- Openmc-FEnicsx for muLtiphysics tutorIAl☆16Updated last week
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆70Updated 3 weeks ago
- Accelerated Discretized Geometry☆17Updated this week
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆26Updated 4 years ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆24Updated 8 months ago
- Contains slides and example problems for OpenMC workshops and presentations☆23Updated 2 years ago
- API for parsing and post-processing many MC simulations related files☆17Updated last week
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated last year