enrico-dev / enrico
ENRICO: Exascale Nuclear Reactor Investigative COde
☆65Updated last year
Alternatives and similar repositories for enrico:
Users that are interested in enrico are comparing it to the libraries listed below
- Stochastic Calculator Of Neutron transport Equation☆42Updated 2 weeks ago
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆17Updated 2 years ago
- open-source Sn software☆32Updated this week
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆40Updated 10 months ago
- List of open source projects related to OpenMC☆25Updated 8 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆112Updated 2 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆57Updated 3 weeks ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- Repository for Moltres, a code for simulating Molten Salt Reactors☆68Updated this week
- Collection of models for reactor physics benchmarks☆52Updated 7 months ago
- ☆22Updated last week
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆26Updated 3 years ago
- Python ENDF Parser☆33Updated 9 months ago
- OpenMC Monte Carlo Code☆17Updated 3 months ago
- High-Fidelity Multiphysics☆107Updated last week
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆53Updated this week
- ☆30Updated 2 months ago
- Openmc-FEnicsx for muLtiphysics tutorIAl☆16Updated 9 months ago
- Collection of scripts for managing data for OpenMC☆31Updated 3 months ago
- Nuclear data processing with legacy NJOY☆106Updated 2 weeks ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Plugins and command extensions for Coreform Cubit☆18Updated 10 months ago
- Workflow and Template Toolkit for Simulation (WATTS)☆30Updated 3 weeks ago
- Native plotting GUI for model design and verification☆57Updated 3 months ago
- Large scale scientific simulation engine☆36Updated last year
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆32Updated this week
- Tools to translate between different CSG geometry types☆37Updated last year
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆33Updated 4 months 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 4 months ago
- Sampling nuclear data and uncertainty☆51Updated last month