fusion-energy / fusion_neutronics_workflow
Combines open source packages to produce an automated fusion specific neutronics workflow
☆14Updated 2 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 selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- ☆15Updated last year
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆11Updated last week
- ☆22Updated this week
- List of open source projects related to OpenMC☆24Updated 8 months ago
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated 8 months ago
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆33Updated 5 months ago
- A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles☆10Updated last year
- Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API☆12Updated last year
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated 3 weeks ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆24Updated 7 months ago
- Python ENDF Parser☆33Updated 9 months ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- Workflow and Template Toolkit for Simulation (WATTS)☆30Updated last week
- Collection of scripts for managing data for OpenMC☆31Updated 3 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆32Updated last week
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆40Updated 10 months ago
- Sampling nuclear data and uncertainty☆51Updated last week
- API for parsing and post-processing many MC simulations related files☆15Updated 3 weeks ago
- Parametric 3-D CAD modeling toolset for stellarator fusion devices☆31Updated this week
- ☆30Updated 2 months ago
- A Python package for parsing FISPACT-II output☆28Updated 3 weeks ago
- Learn how to simulate hydrogen transport with FESTIM☆18Updated 2 weeks ago
- A Python package for downloading h5 cross section files for use in OpenMC.☆13Updated 4 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆10Updated 2 years ago
- XSPlot - Neutron cross section plotter for isotopes☆14Updated last year
- ENDF/B pre-processing codes (PREPRO)☆19Updated last year
- Openmc-FEnicsx for muLtiphysics tutorIAl☆16Updated 9 months ago
- Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS☆102Updated 2 weeks ago
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆19Updated 3 years ago