svalinn / parastellLinks
Parametric 3-D modeling toolset for stellarator fusion devices
☆36Updated 3 weeks ago
Alternatives and similar repositories for parastell
Users that are interested in parastell 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 5 months ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 2 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆34Updated 3 months ago
- open-source Sn software☆44Updated this week
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- List of open source projects related to OpenMC☆28Updated 4 months ago
- Accelerated Discretized Geometry☆18Updated last week
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated last month
- Meshing library for nuclear workflows☆51Updated 3 weeks ago
- Native plotting GUI for model design and verification☆62Updated last month
- Python ENDF Parser☆38Updated last month
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆162Updated last week
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆38Updated 3 months ago
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆32Updated 2 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 4 years ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆24Updated last year
- API for parsing and post-processing many MC simulations related files☆17Updated 3 weeks ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆79Updated last week
- Convert OpenMC Geometry Components to CAD☆20Updated 10 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated last week
- Create parametric 3D fusion reactor CAD and neutronics models☆86Updated last month
- Tool for converting MCNP input files to OpenMC classes/XML☆47Updated 2 weeks ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆116Updated 7 months ago
- Tools to translate between different CSG geometry types☆39Updated 4 months ago
- JADE, a novel nuclear data libraries V&V tool☆32Updated last week
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated 2 years ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- Combines open source packages to produce an automated fusion specific neutronics workflow☆15Updated 3 years ago