fusion-energy / cad_to_h5mLinks
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
Alternatives and similar repositories for cad_to_h5m
Users that are interested in cad_to_h5m are comparing it to the libraries listed below
Sorting:
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- List of open source projects related to OpenMC☆26Updated 2 months ago
- Native plotting GUI for model design and verification☆60Updated 6 months ago
- Learn how to simulate hydrogen transport with FESTIM☆23Updated last week
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 3 weeks ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆33Updated last month
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆42Updated last year
- Collection of scripts for managing data for OpenMC☆33Updated 6 months ago
- Workflow and Template Toolkit for Simulation (WATTS)☆32Updated last month
- ☆31Updated 2 weeks ago
- Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS☆108Updated last week
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated 2 years ago
- open-source Sn software☆37Updated last week
- Sampling nuclear data and uncertainty☆52Updated last month
- Python ENDF Parser☆34Updated last year
- Tools to translate between different CSG geometry types☆39Updated 2 months ago
- JADE, a novel nuclear data libraries V&V tool☆31Updated 2 months ago
- Combines open source packages to produce an automated fusion specific neutronics workflow☆15Updated 3 years ago
- Collection of models for reactor physics benchmarks☆54Updated 10 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆38Updated this week
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- Stochastic Calculator Of Neutron transport Equation☆47Updated last week
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated 11 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated 3 weeks ago
- Openmc-FEnicsx for muLtiphysics tutorIAl☆16Updated 2 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆112Updated 5 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆72Updated last month
- ☆16Updated last year