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
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Collection of scripts for managing data for OpenMC☆29Updated last month
- OpenMC Monte Carlo Code☆17Updated 3 weeks ago
- Native plotting GUI for model design and verification☆55Updated last month
- List of open source projects related to OpenMC☆24Updated 5 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆37Updated last week
- OpenMC wrapped as a Moose App☆16Updated last year
- Toolkit for reading and interacting with ENDF-6 formatted files☆36Updated last week
- Sampling nuclear data and uncertainty☆50Updated last month
- a companion for writing MCNP input decks☆11Updated 3 years ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆55Updated last week
- Simulate PWR,CANDU and VVER reactor (Assembly Model) using OpenMC https://openmc.readthedocs.io/en/stable/☆12Updated 5 years ago
- Some Monte Carlo tools☆47Updated 2 months ago
- ENDF/B pre-processing codes (PREPRO)☆17Updated last year
- Python ENDF Parser☆27Updated 6 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆14Updated 2 weeks ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆60Updated this week
- Direct Accelerated Geometry Monte Carlo Toolkit☆109Updated last week
- Stochastic Calculator Of Neutron transport Equation☆39Updated 3 weeks ago
- Example Jupyter notebooks for OpenMC☆35Updated 3 months ago
- A depletion framework for OpenMC☆14Updated 7 years ago
- ☆75Updated 8 months ago
- A Python package for parsing FISPACT-II output☆26Updated 11 months ago
- NJOY for the 21st Century☆78Updated last year
- ☆18Updated this week
- Plugins and command extensions for Coreform Cubit☆18Updated 8 months ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆28Updated last month
- Tools to translate between different CSG geometry types☆36Updated last year
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆35Updated last week
- Nuclear data processing with legacy NJOY☆102Updated 2 weeks ago