Alternatives and similar repositories for pyMAISE:

Users that are interested in pyMAISE are comparing it to the libraries listed below

• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆24Updated 6 months ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆33Updated 2 months ago
• openmc-dev / openmc-notebooks
  Example Jupyter notebooks for OpenMC
  ☆35Updated this week
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆40Updated last month
• ezsolti / RFP
  ☆30Updated last week
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆64Updated last year
• FRENSIE / FRENSIE
  Framework for REsearch in Nuclear ScIence and Engineering
  ☆14Updated 3 years ago
• Open-Sn / opensn
  open-source Sn software
  ☆25Updated this week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆37Updated 2 weeks ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆55Updated last month
• dassh-dev / dassh
  Ducted Assembly Steady State Heat Transfer Software (DASSH)
  ☆17Updated last year
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆14Updated last month
• mit-crpg / openmc-reactor-examples
  Catalogs a plethora of reactor inputs for OpenMC
  ☆23Updated this week
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆60Updated last week
• openmsr / msr-archive
  curated documents pertaining to early molten salt reactor research.
  ☆22Updated 11 months ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆36Updated last year
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆29Updated last month
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆55Updated 2 weeks ago
• jlanversin / ONIX
  ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…
  ☆39Updated 2 months ago
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated last year
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆40Updated 8 months ago
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆16Updated 3 months ago
• paulromano / endf-python
  Python ENDF Parser
  ☆28Updated 7 months ago
• eepeterson / openmc_fusion_benchmarks
  ☆18Updated last week
• idaholab / virtual_test_bed
  The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository
  ☆52Updated this week
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆25Updated 6 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆50Updated last month