ahmedkmadani / OpenMCProjectLinks
Simulate PWR,CANDU and VVER reactor (Assembly Model) using OpenMC https://openmc.readthedocs.io/en/stable/
☆14Updated 6 years ago
Alternatives and similar repositories for OpenMCProject
Users that are interested in OpenMCProject are comparing it to the libraries listed below
Sorting:
- 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 7 months ago
- Native plotting GUI for model design and verification☆64Updated last month
- Tool for converting MCNP input files to OpenMC classes/XML☆52Updated last month
- a companion for writing MCNP input decks☆12Updated 4 years ago
- Python ENDF Parser☆39Updated 2 months ago
- Collection of scripts for managing data for OpenMC☆38Updated 2 weeks ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆172Updated last month
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 6 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆40Updated 2 weeks ago
- Catalogs a plethora of reactor inputs for OpenMC☆35Updated 10 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆49Updated this week
- Example Jupyter notebooks for OpenMC☆40Updated 10 months ago
- ENDF/B pre-processing codes (PREPRO)☆22Updated 2 years ago
- Tools to translate between different CSG geometry types☆40Updated 7 months ago
- Stochastic Calculator Of Neutron transport Equation☆53Updated 3 weeks ago
- Sampling nuclear data and uncertainty☆54Updated 3 months ago
- Nuclear data processing with legacy NJOY☆123Updated 3 weeks 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 last year
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- API for parsing and post-processing many MC simulations related files☆17Updated 3 weeks ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆41Updated last month
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated last week
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆14Updated 8 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆35Updated 6 months ago
- Convert OpenMC Geometry Components to CAD☆20Updated last year
- NJOY for the 21st Century☆84Updated last year
- A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles☆12Updated last year
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆18Updated last month
- ☆33Updated 5 months ago