Alternatives and similar repositories for msre

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

• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆59Updated 5 months ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆44Updated 2 weeks ago
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆65Updated last year
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆38Updated 3 weeks ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆58Updated 2 months ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆70Updated last month
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆33Updated 5 months ago
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated 2 weeks ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated last month
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆26Updated 3 weeks ago
• fusion-energy / openmc-plasma-source
  Creates a plasma source as an openmc.source object from input parameters that describe the plasma
  ☆36Updated this week
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆29Updated 3 weeks ago
• paulromano / endf-python
  Python ENDF Parser
  ☆33Updated 10 months ago
• KDSource / KDSource
  Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.
  ☆22Updated last month
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆18Updated 7 months ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆42Updated last month
• openmsr / msr-archive
  curated documents pertaining to early molten salt reactor research.
  ☆22Updated last year
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆111Updated 4 months ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆47Updated 2 weeks ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆51Updated last week
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated last week
• fispact / pypact
  A Python package for parsing FISPACT-II output
  ☆29Updated last month
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆32Updated this week
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆18Updated 4 months ago
• Open-Sn / opensn
  open-source Sn software
  ☆35Updated this week
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆53Updated 8 months ago
• IAEA-NDS / open-benchmarks
  Computational inputs, reference outputs and experimental data for V&V systems
  ☆13Updated 2 months ago
• fusion-energy / neutronics_material_maker
  A tool for making reproducible materials and standardizing use across several neutronics codes
  ☆24Updated 8 months ago
• pshriwise / xdg
  Accelerated Discretized Geometry
  ☆17Updated last week