fusion-energy / fusion_neutronics_workflowLinks
Combines open source packages to produce an automated fusion specific neutronics workflow
☆15Updated 3 years ago
Alternatives and similar repositories for fusion_neutronics_workflow
Users that are interested in fusion_neutronics_workflow are comparing it to the libraries listed below
Sorting:
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆14Updated 7 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated this week
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 3 years ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆34Updated 5 months ago
- List of open source projects related to OpenMC☆30Updated 6 months ago
- Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API☆11Updated 2 years ago
- Native plotting GUI for model design and verification☆64Updated 2 weeks ago
- Parametric 3-D modeling toolset for stellarator fusion devices☆38Updated 2 weeks ago
- Open-source Sn software☆52Updated this week
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆17Updated this week
- Python ENDF Parser☆39Updated last month
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated last year
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles☆12Updated last year
- Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS☆113Updated last week
- ☆33Updated 4 months ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆39Updated 5 months ago
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 5 months ago
- Tools to translate between different CSG geometry types☆40Updated 6 months ago
- Convert OpenMC Geometry Components to CAD☆20Updated last year
- A tool for making reproducible materials and standardizing use across several neutronics codes☆25Updated last year
- Tool for converting MCNP input files to OpenMC classes/XML☆52Updated last week
- Accelerated Discretized Geometry☆19Updated last week
- ☆16Updated last year
- JADE, a novel nuclear data libraries V&V tool☆34Updated this week
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆32Updated 2 weeks ago
- API for parsing and post-processing many MC simulations related files☆17Updated last month