aims-umich / pyMAISELinks
Machine learning and artificial intelligence benchmarking library for nuclear engineering applications.
☆30Updated 3 months ago
Alternatives and similar repositories for pyMAISE
Users that are interested in pyMAISE are comparing it to the libraries listed below
Sorting:
- Stochastic Calculator Of Neutron transport Equation☆50Updated last week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆39Updated 3 weeks ago
- List of open source projects related to OpenMC☆27Updated 3 months ago
- Framework for REsearch in Nuclear ScIence and Engineering☆15Updated 3 years ago
- ☆32Updated last month
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Example Jupyter notebooks for OpenMC☆38Updated 6 months ago
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆20Updated last month
- Native plotting GUI for model design and verification☆60Updated last week
- Collection of scripts for managing data for OpenMC☆34Updated 7 months ago
- Neutronics, Thermal-hydraulics and Structure Multi-physics Coupled Simulation of Heat Pipe Reactor☆12Updated 5 years ago
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆60Updated this week
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- High-Fidelity Multiphysics☆119Updated 3 weeks ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆158Updated last week
- Tool for converting MCNP input files to OpenMC classes/XML☆44Updated 3 months ago
- Accelerated Discretized Geometry☆18Updated 3 weeks ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 4 months ago
- Convert OpenMC Geometry Components to CAD☆18Updated 9 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…☆41Updated 8 months ago
- API for parsing and post-processing many MC simulations related files☆17Updated 3 weeks ago
- open-source Sn software☆39Updated this week
- ENRICO: Exascale Nuclear Reactor Investigative COde☆67Updated 2 years ago
- Python ENDF Parser☆35Updated 2 weeks ago
- Tools to translate between different CSG geometry types☆39Updated 3 months ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated last month
- Direct Accelerated Geometry Monte Carlo Toolkit☆114Updated 6 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆74Updated 2 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆33Updated last month
- Nuclear data processing with legacy NJOY☆117Updated this week