tarekbardouni / 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).
☆29Updated 11 months ago
Alternatives and similar repositories for ERSN-OpenMC
Users that are interested in ERSN-OpenMC are comparing it to the libraries listed below
Sorting:
- Collection of scripts for managing data for OpenMC☆31Updated 4 months ago
- Simulation of transmutation and decay in nuclear systems☆28Updated 4 months ago
- Repository for Moltres, a code for simulating Molten Salt Reactors☆68Updated last week
- ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Ba…☆13Updated 7 years ago
- Online reprocessing for molten salt reactors☆20Updated 3 weeks ago
- Native plotting GUI for model design and verification☆57Updated 3 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆57Updated last month
- Monte Carlo Particle Lists☆30Updated this week
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- detailed cad model of the msre☆36Updated 2 months ago
- Stochastic Calculator Of Neutron transport Equation☆43Updated last week
- Format description for ACE nuclear data files☆21Updated 3 years ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated last year
- continuous energy monte carlo neutron transport in general geometries on GPUs☆43Updated 7 years ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆32Updated last week
- The Cyclus Nuclear Fuel Cycle Simulator☆82Updated this week
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆39Updated 5 months ago
- Nuclear Reactor Theory☆19Updated 7 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆41Updated 3 months ago
- MC/DC: Monte Carlo Dynamic Code☆41Updated 3 weeks ago
- Collection of models for reactor physics benchmarks☆52Updated 7 months ago
- Tools to translate between different CSG geometry types☆37Updated last year
- A Python package for parsing FISPACT-II output☆28Updated 3 weeks ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆24Updated 7 months ago
- Large scale scientific simulation engine☆37Updated last year
- Direct Accelerated Geometry Monte Carlo Toolkit☆112Updated 3 months ago
- Sampling nuclear data and uncertainty☆51Updated last week
- An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool☆24Updated 4 years ago
- Python ENDF Parser☆33Updated 9 months ago