fusion-energy / neutronics-workshopLinks
A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
☆156Updated this week
Alternatives and similar repositories for neutronics-workshop
Users that are interested in neutronics-workshop are comparing it to the libraries listed below
Sorting:
- Native plotting GUI for model design and verification☆60Updated 6 months ago
- List of open source projects related to OpenMC☆26Updated 2 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 3 months ago
- Tools to translate between different CSG geometry types☆39Updated 2 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆72Updated last month
- Direct Accelerated Geometry Monte Carlo Toolkit☆112Updated 5 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Python ENDF Parser☆34Updated last year
- Stochastic Calculator Of Neutron transport Equation☆47Updated last week
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- Tool for converting MCNP input files to OpenMC classes/XML☆44Updated 2 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆38Updated this week
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 3 weeks ago
- JADE, a novel nuclear data libraries V&V tool☆31Updated 2 months ago
- API for parsing and post-processing many MC simulations related files☆17Updated last week
- Sampling nuclear data and uncertainty☆52Updated last month
- High-Fidelity Multiphysics☆116Updated this week
- Example Jupyter notebooks for OpenMC☆37Updated 5 months ago
- ☆83Updated last year
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆33Updated last month
- NJOY for the 21st Century☆79Updated last year
- Nuclear data processing with legacy NJOY☆113Updated last week
- Meshing library for nuclear workflows☆51Updated 4 months ago
- Create parametric 3D fusion reactor CAD and neutronics models☆86Updated this week
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆42Updated last year
- Workflow and Template Toolkit for Simulation (WATTS)☆32Updated last month
- Convert OpenMC Geometry Components to CAD☆18Updated 8 months ago
- ☆31Updated 2 weeks ago
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆22Updated 2 months ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated last week