festim-dev / FESTIM-workshopLinks
Learn how to simulate hydrogen transport with FESTIM
☆27Updated this week
Alternatives and similar repositories for FESTIM-workshop
Users that are interested in FESTIM-workshop are comparing it to the libraries listed below
Sorting:
- Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS☆115Updated this week
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 3 weeks ago
- ☆33Updated 6 months ago
- Openmc-FEnicsx for muLtiphysics tutorIAl☆16Updated 8 months ago
- Python ENDF Parser☆39Updated last week
- Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API☆11Updated 2 years ago
- API for parsing and post-processing many MC simulations related files☆17Updated last week
- List of open source projects related to OpenMC☆31Updated 8 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆85Updated 2 months ago
- Native plotting GUI for model design and verification☆64Updated last week
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- Stochastic Calculator Of Neutron transport Equation☆55Updated 2 weeks ago
- JADE, a novel nuclear data libraries V&V tool☆34Updated 3 weeks ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆175Updated this week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆41Updated last month
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆21Updated 7 months ago
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆64Updated this week
- Open-source Sn software☆58Updated this week
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆52Updated this week
- Tools to translate between different CSG geometry types☆40Updated 8 months ago
- Accelerated Discretized Geometry☆23Updated 3 weeks ago
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago
- Convert OpenMC Geometry Components to CAD☆20Updated last year
- A nuclear reactor lattice physics code.☆20Updated last week
- Tool for converting MCNP input files to OpenMC classes/XML☆53Updated last month
- High-Fidelity Multiphysics☆123Updated this week
- Meshing library for nuclear workflows☆70Updated last month
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 7 months ago
- Catalogs a plethora of reactor inputs for OpenMC☆35Updated 11 months ago