RemDelaporteMathurin / h-transport-materialsLinks
Easily access hydrogen transport properties
☆18Updated 8 months ago
Alternatives and similar repositories for h-transport-materials
Users that are interested in h-transport-materials are comparing it to the libraries listed below
Sorting:
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated last month
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated 11 months ago
- Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS☆109Updated 2 weeks ago
- A Python package for downloading h5 cross section files for use in OpenMC.☆14Updated 7 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- Parametric 3-D modeling toolset for stellarator fusion devices☆34Updated this week
- Tool to estimate H retention in tokamak divertors☆10Updated 3 years ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆24Updated 10 months ago
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆36Updated 2 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated this week
- Native plotting GUI for model design and verification☆60Updated last week
- JADE, a novel nuclear data libraries V&V tool☆32Updated 2 months ago
- XSPlot - Neutron cross section plotter for isotopes☆14Updated 2 years ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆12Updated 3 months ago
- Python ENDF Parser☆35Updated 2 weeks ago
- Learn how to simulate hydrogen transport with FESTIM☆23Updated 3 weeks ago
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆31Updated last month
- Openmc-FEnicsx for muLtiphysics tutorIAl☆16Updated 3 months ago
- List of open source projects related to OpenMC☆27Updated 3 months ago
- Create parametric 3D fusion reactor CAD and neutronics models☆87Updated 3 weeks ago
- Sampling nuclear data and uncertainty☆52Updated 2 weeks ago
- Combines open source packages to produce an automated fusion specific neutronics workflow☆15Updated 3 years ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆33Updated last month
- open-source Sn software☆39Updated this week
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆74Updated 2 months ago
- Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API☆11Updated last year
- Meshing library for nuclear workflows☆50Updated this week
- Accelerated Discretized Geometry☆18Updated 3 weeks ago