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
☆11Updated 2 years ago
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:
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- List of open source projects related to OpenMC☆30Updated 6 months ago
- Native plotting GUI for model design and verification☆64Updated last week
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated this week
- Python ENDF Parser☆39Updated last month
- Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS☆113Updated last week
- Openmc-FEnicsx for muLtiphysics tutorIAl☆16Updated 6 months ago
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago
- ☆32Updated 4 months ago
- Collection of scripts for managing data for OpenMC☆38Updated last week
- Open-source Sn software☆52Updated this week
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 5 months ago
- Learn how to simulate hydrogen transport with FESTIM☆27Updated last month
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 3 years ago
- JADE, a novel nuclear data libraries V&V tool☆34Updated this week
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆28Updated 4 years ago
- Collection of models for reactor physics benchmarks☆57Updated 2 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆118Updated 9 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆81Updated this week
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆34Updated 5 months ago
- Stochastic Calculator Of Neutron transport Equation☆53Updated last week
- ENRICO: Exascale Nuclear Reactor Investigative COde☆66Updated 2 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆52Updated last week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆40Updated 2 months ago
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆42Updated 11 months ago
- ENDF/B pre-processing codes (PREPRO)☆21Updated 2 years ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆17Updated last month
- OpenMC Monte Carlo Code☆23Updated 10 months ago