fusion-energy / fusion_neutronics_workflowLinks
Combines open source packages to produce an automated fusion specific neutronics workflow
☆15Updated 3 years ago
Alternatives and similar repositories for fusion_neutronics_workflow
Users that are interested in fusion_neutronics_workflow are comparing it to the libraries listed below
Sorting:
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆11Updated 2 months ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated this week
- 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 last month
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆41Updated last year
- Native plotting GUI for model design and verification☆59Updated 5 months ago
- Python ENDF Parser☆34Updated 11 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- open-source Sn software☆36Updated this week
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated last week
- Tool for converting MCNP input files to OpenMC classes/XML☆43Updated last month
- Accelerated Discretized Geometry☆17Updated last week
- JADE, a novel nuclear data libraries V&V tool☆31Updated last month
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆36Updated 3 weeks ago
- ☆31Updated 3 weeks ago
- Convert OpenMC Geometry Components to CAD☆18Updated 7 months ago
- Sampling nuclear data and uncertainty☆52Updated 3 weeks ago
- 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
- API for parsing and post-processing many MC simulations related files☆17Updated this week
- Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS☆107Updated 2 weeks ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆47Updated this week
- Workflow and Template Toolkit for Simulation (WATTS)☆32Updated 3 weeks ago
- Tool to estimate H retention in tokamak divertors☆10Updated 3 years ago
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated 10 months ago
- Openmc-FEnicsx for muLtiphysics tutorIAl☆16Updated last month
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆41Updated 7 months ago
- Stochastic Calculator Of Neutron transport Equation☆45Updated last week
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆71Updated 3 weeks ago
- curated documents pertaining to early molten salt reactor research.☆22Updated last year