festim-dev / FESTIM-workshop
Learn how to simulate hydrogen transport with FESTIM
☆18Updated 2 months ago
Alternatives and similar repositories for FESTIM-workshop:
Users that are interested in FESTIM-workshop are comparing it to the libraries listed below
- Easily access hydrogen transport properties☆15Updated last month
- Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS☆98Updated this week
- ☆18Updated this week
- 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
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated 5 months ago
- ☆29Updated this week
- OpenMC wrapped as a Moose App☆16Updated last year
- List of open source projects related to OpenMC☆24Updated 5 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆14Updated 2 weeks ago
- Python ENDF Parser☆27Updated 6 months ago
- A Python package for downloading h5 cross section files for use in OpenMC.☆12Updated last month
- open-source Sn software☆25Updated this week
- Convert OpenMC Geometry Components to CAD☆16Updated 3 months ago
- Combines open source packages to produce an automated fusion specific neutronics workflow☆14Updated 2 years ago
- PROCESS is a systems code at UKAEA that calculates in a self-consistent manner the parameters of a fusion power plant with a specified pe…☆43Updated this week
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆40Updated 7 months ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆11Updated 9 months ago
- ☆13Updated 10 months ago
- Tool to estimate H retention in tokamak divertors☆10Updated 3 years ago
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 5 months ago
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆32Updated 2 months ago
- Native plotting GUI for model design and verification☆55Updated last month
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆60Updated this week
- XSPlot - Neutron cross section plotter for isotopes☆14Updated last year
- JADE, a novel nuclear data libraries V&V tool☆25Updated this week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆34Updated last month
- Create parametric 3D fusion reactor CAD and neutronics models☆73Updated last week
- Parametric 3-D CAD modeling toolset for stellarator fusion devices☆28Updated this week