svalinn / parastellLinks
Parametric 3-D modeling toolset for stellarator fusion devices
☆38Updated 2 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 7 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆34Updated 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 last week
- Open-source Sn software☆52Updated last week
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆17Updated this week
- List of open source projects related to OpenMC☆30Updated 6 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 3 years ago
- Accelerated Discretized Geometry☆19Updated last week
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago
- Python ENDF Parser☆39Updated last month
- Native plotting GUI for model design and verification☆64Updated 2 weeks ago
- Create parametric 3D fusion reactor CAD and neutronics models☆88Updated 3 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- Meshing library for nuclear workflows☆65Updated 3 weeks ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆171Updated this week
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆39Updated 5 months ago
- Tools to translate between different CSG geometry types☆40Updated 6 months ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆25Updated last year
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated last year
- Convert OpenMC Geometry Components to CAD☆20Updated last year
- Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS☆113Updated 2 weeks ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆81Updated last week
- JADE, a novel nuclear data libraries V&V tool☆34Updated last week
- Stochastic Calculator Of Neutron transport Equation☆53Updated this week
- This is the GitHub repository for STELLOPT, the state-of-the-art stellarator optimization code.☆102Updated last week
- Example Jupyter notebooks for OpenMC☆40Updated 9 months ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆66Updated 2 years ago
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆32Updated 3 weeks ago
- Bluemira is an integrated inter-disciplinary design tool for future fusion reactors. It incorporates several modules, some of which rely …☆92Updated this week