ERMETE-Lab / MP-OFELIALinks
Openmc-FEnicsx for muLtiphysics tutorIAl
☆16Updated last month
Alternatives and similar repositories for MP-OFELIA
Users that are interested in MP-OFELIA are comparing it to the libraries listed below
Sorting:
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated this week
- Convert OpenMC Geometry Components to CAD☆18Updated 7 months ago
- open-source Sn software☆36Updated this week
- Stochastic Calculator Of Neutron transport Equation☆45Updated last week
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆18Updated last week
- In this project we develop an OpenNTP package to solve the multi-group neutron transport equation.☆13Updated 4 years ago
- ☆31Updated 3 weeks ago
- Vim plugin for MOOSE Framework input file format☆13Updated last week
- Neutronics, Thermal-hydraulics and Structure Multi-physics Coupled Simulation of Heat Pipe Reactor☆10Updated 5 years ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆41Updated last year
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆57Updated last week
- API for parsing and post-processing many MC simulations related files☆17Updated 3 weeks ago
- Collection of models for reactor physics benchmarks☆54Updated 9 months ago
- Learn how to simulate hydrogen transport with FESTIM☆22Updated this week
- A MOOSE-based app to enable finite element problem setup using the MFEM FE library.☆18Updated 3 weeks ago
- List of open source projects related to OpenMC☆26Updated last month
- Python ENDF Parser☆34Updated 11 months ago
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆27Updated 4 years ago
- Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS☆107Updated 2 weeks ago
- Zero-order Reaction Kinetics (Zero-RK) is a software package that simulates chemically reacting systems in a computationally efficient ma…☆41Updated last month
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆40Updated 7 months ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆71Updated 3 weeks ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated last week
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated last year
- ☆44Updated 2 years ago
- Python framework for Nek5000☆29Updated last week
- Examples for Nek5000☆38Updated 4 years ago