EL-Bakkali-Jaafar / ERSN-OpenMC
ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Bakkali & Tarek EL Bardouni, members of Radiation and Nuclear Systems Group ERSN at University Abdelmalek Essaady in Tetouan (Morocco).
☆13Updated 7 years ago
Alternatives and similar repositories for ERSN-OpenMC:
Users that are interested in ERSN-OpenMC are comparing it to the libraries listed below
- Collection of scripts for managing data for OpenMC☆31Updated 3 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- OpenMC wrapped as a Moose App☆16Updated last year
- Native plotting GUI for model design and verification☆57Updated 3 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆40Updated 2 months ago
- OpenMC Monte Carlo Code☆17Updated 2 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆57Updated last week
- ENDF/B pre-processing codes (PREPRO)☆19Updated last year
- A depletion framework for OpenMC☆14Updated 7 years ago
- List of open source projects related to OpenMC☆25Updated 7 months ago
- Sampling nuclear data and uncertainty☆51Updated last month
- a companion for writing MCNP input decks☆12Updated 4 years ago
- Tools to translate between different CSG geometry types☆37Updated last year
- Python ENDF Parser☆32Updated 8 months ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated last year
- Collection of models for reactor physics benchmarks☆52Updated 6 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated this week
- Contains slides and example problems for OpenMC workshops and presentations☆23Updated 2 years ago
- Stochastic Calculator Of Neutron transport Equation☆42Updated last week
- Simulate PWR,CANDU and VVER reactor (Assembly Model) using OpenMC https://openmc.readthedocs.io/en/stable/☆12Updated 5 years ago
- ☆21Updated 2 weeks ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆39Updated 3 weeks ago
- Some Monte Carlo tools☆48Updated last month
- Plugins and command extensions for Coreform Cubit☆18Updated 10 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆33Updated 3 weeks ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆41Updated this week
- NJOY for the 21st Century☆78Updated last year
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆40Updated 9 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆112Updated 2 months ago
- ☆77Updated 10 months ago