festim-dev / FESTIM
Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS
☆92Updated this week
Related projects ⓘ
Alternatives and complementary repositories for FESTIM
- Learn how to simulate hydrogen transport with FESTIM☆17Updated last month
- Easily access hydrogen transport properties☆15Updated last week
- ☆17Updated 3 months ago
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated 2 months ago
- Tool to estimate H retention in tokamak divertors☆10Updated 3 years ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆36Updated 4 months ago
- open-source Sn software☆21Updated this week
- A Python package for downloading h5 cross section files for use in OpenMC.☆11Updated last year
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆28Updated this week
- Meshing library for nuclear workflows☆42Updated last month
- SFINCS: the Stellarator Fokker-Planck Iterative Neoclassical Conservative Solver☆23Updated last month
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆12Updated 5 months ago
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 2 months ago
- OpenMC wrapped as a Moose App☆16Updated last year
- Vim plugin for MOOSE Framework input file format☆12Updated last year
- 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
- ☆17Updated 2 years ago
- Python ENDF Parser☆26Updated 3 months ago
- ☆29Updated last year
- Stochastic Calculator Of Neutron transport Equation☆36Updated last month
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆17Updated last year
- 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…☆36Updated this week
- List of open source projects related to OpenMC☆21Updated 2 months ago
- Native plotting GUI for model design and verification☆48Updated 3 weeks ago
- XSPlot - Neutron cross section plotter for isotopes☆14Updated last year
- Heat flux Engineering Analysis Toolkit☆53Updated 3 weeks ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆20Updated last month
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆10Updated 2 years ago
- A collection of files that can be used as inputs in the codes commonly used in the Plasma Physics community.☆38Updated last month