tarekbardouni / ERSN-OpenMCLinks
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).
☆30Updated last year
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☆33Updated 4 months ago
- Simulation of transmutation and decay in nuclear systems☆28Updated 4 months ago
- 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
- Repository for Moltres, a code for simulating Molten Salt Reactors☆68Updated last week
- Online reprocessing for molten salt reactors☆20Updated last month
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆57Updated last month
- Native plotting GUI for model design and verification☆58Updated 4 months ago
- Sampling nuclear data and uncertainty☆51Updated last month
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated last year
- The Cyclus Nuclear Fuel Cycle Simulator☆82Updated this week
- Monte Carlo Particle Lists☆32Updated last week
- 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 2 years ago
- 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
- detailed cad model of the msre☆36Updated 3 months ago
- Format description for ACE nuclear data files☆21Updated 3 years ago
- Nuclear Reactor Theory☆19Updated 7 years ago
- JADE, a novel nuclear data libraries V&V tool☆29Updated this week
- List of open source projects related to OpenMC☆26Updated last week
- Direct Accelerated Geometry Monte Carlo Toolkit☆112Updated 3 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆32Updated 2 weeks ago
- Plugins and command extensions for Coreform Cubit☆18Updated last year
- Nuclear data processing with legacy NJOY☆109Updated 2 weeks ago
- Tools to translate between different CSG geometry types☆38Updated last week
- Contains slides and example problems for OpenMC workshops and presentations☆23Updated 2 years ago
- An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool☆24Updated 4 years ago
- Collection of models for reactor physics benchmarks☆52Updated 8 months ago
- continuous energy monte carlo neutron transport in general geometries on GPUs☆43Updated 8 years ago
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆36Updated 5 months ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆24Updated 8 months ago