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 selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆12Updated 3 months ago
- Native plotting GUI for model design and verification☆60Updated 6 months ago
- List of open source projects related to OpenMC☆26Updated 2 months ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 3 weeks ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆33Updated last month
- Python ENDF Parser☆34Updated last year
- Parametric 3-D CAD modeling toolset for stellarator fusion devices☆34Updated last week
- open-source Sn software☆37Updated last week
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆42Updated last year
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- 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
- ☆16Updated last year
- Workflow and Template Toolkit for Simulation (WATTS)☆32Updated last month
- Sampling nuclear data and uncertainty☆52Updated last month
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆36Updated last month
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS☆108Updated last week
- Collection of scripts for managing data for OpenMC☆33Updated 6 months ago
- Tools to translate between different CSG geometry types☆39Updated 2 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated 3 weeks ago
- API for parsing and post-processing many MC simulations related files☆17Updated last week
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆44Updated 2 months ago
- ENDF/B pre-processing codes (PREPRO)☆19Updated last year
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆29Updated last week
- ☆31Updated 2 weeks ago
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆41Updated 7 months ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆24Updated 10 months ago
- JADE, a novel nuclear data libraries V&V tool☆31Updated 2 months ago