Alternatives and similar repositories for pypact:

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

• eepeterson / openmc_fusion_benchmarks
  ☆22Updated last week
• paulromano / endf-python
  Python ENDF Parser
  ☆33Updated 9 months ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated 2 weeks ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆15Updated 2 weeks ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆25Updated 8 months ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆26Updated last week
• jlball / arc-nonproliferation
  An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.
  ☆11Updated 8 months ago
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆19Updated last year
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆11Updated last year
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆43Updated 3 weeks ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆40Updated 2 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆51Updated last month
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆37Updated last year
• pshriwise / xdg
  Accelerated Discretized Geometry
  ☆13Updated last week
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆40Updated last week
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆57Updated 3 months ago
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆17Updated 5 months ago
• toshihikokawano / DeCE
  ENDF-6 data interface and nuclear data evaluation assist code
  ☆16Updated last week
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆31Updated 3 months ago
• ezsolti / RFP
  ☆30Updated 2 months ago
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆30Updated this week
• ukaea / neutronics_material_maker
  A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak
  ☆19Updated 3 years ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆57Updated 3 weeks ago
• lanl / mcnptools
  ☆77Updated 11 months ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆42Updated this week
• Open-Sn / opensn
  open-source Sn software
  ☆32Updated last week
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆69Updated 3 weeks ago
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆29Updated 2 weeks ago
• IAEA-NDS / endf-parserpy
  Python package for reading, writing, verifying and translating ENDF-6 formatted files
  ☆15Updated last month