aims-umich / pyMAISELinks
Machine learning and artificial intelligence benchmarking library for nuclear engineering applications.
☆29Updated 6 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☆51Updated 3 weeks ago
- ☆32Updated 4 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆40Updated last month
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- List of open source projects related to OpenMC☆30Updated 5 months ago
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆63Updated this week
- Example Jupyter notebooks for OpenMC☆40Updated 8 months ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆168Updated last week
- Native plotting GUI for model design and verification☆64Updated last month
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated last month
- Collection of scripts for managing data for OpenMC☆38Updated last week
- Python ENDF Parser☆39Updated 3 weeks ago
- Framework for REsearch in Nuclear ScIence and Engineering☆15Updated 4 years ago
- Neutronics, Thermal-hydraulics and Structure Multi-physics Coupled Simulation of Heat Pipe Reactor☆12Updated 5 years ago
- open-source Sn software☆49Updated this week
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated 2 years ago
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆21Updated 4 months ago
- High-Fidelity Multiphysics☆120Updated this week
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 4 months ago
- Catalogs a plethora of reactor inputs for OpenMC☆34Updated 8 months ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- Accelerated Discretized Geometry☆18Updated last week
- API for parsing and post-processing many MC simulations related files☆17Updated 3 weeks ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆118Updated 9 months ago
- Sampling nuclear data and uncertainty☆53Updated 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…☆42Updated 11 months ago
- Collection of validation scripts, notebooks, results☆11Updated 2 years ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated last week
- THOR is a radiation transport code for unstructured meshes.☆16Updated last year
- A nuclear reactor lattice physics code.☆17Updated this week