fusion-energy / neutronics-workshop
A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
☆118Updated 2 months ago
Related projects: ⓘ
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆52Updated 3 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆53Updated last month
- ☆61Updated 3 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆33Updated last month
- Native plotting GUI for model design and verification☆45Updated last month
- Python ENDF Parser☆25Updated last month
- Stochastic Calculator Of Neutron transport Equation☆34Updated last week
- Thermal Scattering Library created with NJOY+NCrystal☆9Updated 2 years ago
- Example Jupyter notebooks for OpenMC☆26Updated 2 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆97Updated last month
- Tools to translate between different CSG geometry types☆32Updated last year
- Sampling nuclear data and uncertainty☆47Updated 2 weeks ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆31Updated 3 years ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆30Updated this week
- A Python package for parsing FISPACT-II output☆25Updated 6 months ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆33Updated last week
- Create parametric 3D fusion reactor CAD and neutronics models☆61Updated 3 months ago
- List of open source projects related to OpenMC☆19Updated 3 weeks ago
- curated documents pertaining to early molten salt reactor research.☆20Updated 6 months ago
- JADE, a novel nuclear data libraries V&V tool☆23Updated last month
- Meshing library for nuclear workflows☆41Updated last month
- ENRICO: Exascale Nuclear Reactor Investigative COde☆61Updated last year
- Nuclear data processing with legacy NJOY☆96Updated last month
- Contains slides and example problems for OpenMC workshops and presentations☆23Updated 2 years ago
- Catalogs a plethora of reactor inputs for OpenMC☆18Updated 3 years ago
- Monte Carlo Particle Lists☆28Updated 6 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆12Updated 3 months ago
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆26Updated last month
- High-Fidelity Multiphysics☆89Updated last week