aurora-multiphysics / auroraLinks
Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
☆43Updated last year
Alternatives and similar repositories for aurora
Users that are interested in aurora are comparing it to the libraries listed below
Sorting:
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated this week
- ENRICO: Exascale Nuclear Reactor Investigative COde☆66Updated 2 years ago
- open-source Sn software☆50Updated last week
- List of open source projects related to OpenMC☆30Updated 6 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆34Updated 5 months ago
- Python ENDF Parser☆39Updated last month
- Stochastic Calculator Of Neutron transport Equation☆53Updated last week
- A tool for making reproducible materials and standardizing use across several neutronics codes☆25Updated last year
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆17Updated last month
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 3 years ago
- Parametric 3-D modeling toolset for stellarator fusion devices☆38Updated last week
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 5 months ago
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆28Updated 4 years ago
- Native plotting GUI for model design and verification☆64Updated last week
- Collection of scripts for managing data for OpenMC☆38Updated this week
- ☆32Updated 4 months ago
- High-Fidelity Multiphysics☆120Updated last week
- Collection of models for reactor physics benchmarks☆57Updated 2 months ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆14Updated 7 months ago
- JADE, a novel nuclear data libraries V&V tool☆34Updated this week
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- Tools to translate between different CSG geometry types☆40Updated 6 months ago
- Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS☆113Updated last week
- Convert OpenMC Geometry Components to CAD☆20Updated last year
- Direct Accelerated Geometry Monte Carlo Toolkit☆118Updated 9 months ago
- Accelerated Discretized Geometry☆19Updated last week
- Three-Dimensional Discrete Ordinates Neutron, Photon, Electron and Positron Transport Code☆11Updated 3 years 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
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago