svalinn / parastell
Parametric 3-D CAD modeling toolset for stellarator fusion devices
☆28Updated this week
Alternatives and similar repositories for parastell:
Users that are interested in parastell are comparing it to the libraries listed below
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆32Updated 2 months ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆11Updated 9 months ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆40Updated 7 months ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆23Updated 4 months ago
- ☆18Updated this week
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆32Updated 3 weeks ago
- Meshing library for nuclear workflows☆46Updated 2 months ago
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 5 months ago
- Create parametric 3D fusion reactor CAD and neutronics models☆73Updated last week
- List of open source projects related to OpenMC☆24Updated 5 months ago
- Python ENDF Parser☆27Updated 6 months ago
- Collection of scripts for managing data for OpenMC☆29Updated last month
- Monte Carlo Particle Lists☆30Updated 11 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆60Updated last week
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- A Python package for parsing FISPACT-II output☆26Updated 11 months ago
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated 5 months ago
- This is an umbrella project for the stellarator community tools.☆19Updated 3 months ago
- Stochastic Calculator Of Neutron transport Equation☆39Updated 3 weeks ago
- Sampling nuclear data and uncertainty☆50Updated last month
- 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
- Example Jupyter notebooks for OpenMC☆35Updated 2 months ago
- Bluemira is an integrated inter-disciplinary design tool for future fusion reactors. It incorporates several modules, some of which rely …☆68Updated this week
- Native plotting GUI for model design and verification☆55Updated 3 weeks ago
- OpenMC Monte Carlo Code☆17Updated 2 weeks ago
- Easily access hydrogen transport properties☆15Updated last month
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆14Updated 2 weeks ago
- ☆13Updated 10 months ago
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆20Updated 4 months ago