Alternatives and similar repositories for x4i3

Users that are interested in x4i3 are comparing it to the libraries listed below

• paulromano / endf-python
  Python ENDF Parser
  ☆36Updated last month
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated 2 weeks ago
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated 2 months ago
• AnderGray / openmc_uq_sinbad
  Repository for running SINBAD benchmarks with OpenMC and UQ
  ☆10Updated 3 years ago
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 2 years ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆32Updated this week
• toshihikokawano / DeCE
  ENDF-6 data interface and nuclear data evaluation assist code
  ☆16Updated 4 months ago
• jlball / arc-nonproliferation
  An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.
  ☆11Updated last year
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆27Updated 3 months ago
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆13Updated 4 months ago
• pshriwise / xdg
  Accelerated Discretized Geometry
  ☆18Updated last week
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆40Updated 3 weeks ago
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated last month
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆48Updated this week
• ukaea / SpaceClaim_API_NeutronicsTools
  Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis
  ☆14Updated 4 years ago
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆30Updated last month
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆45Updated last week
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 4 years ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆52Updated this week
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆76Updated 2 months ago
• fispact / pypact
  A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact
  ☆31Updated last month
• njoy / NJOY21
  NJOY for the 21st Century
  ☆80Updated last year
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆18Updated 9 months ago
• openmc-data-storage / openmc_data_downloader
  A Python package for downloading h5 cross section files for use in OpenMC.
  ☆14Updated 8 months ago
• Open-Sn / opensn
  open-source Sn software
  ☆42Updated this week
• IAEA-NDS / endf-parserpy
  Python package for reading, writing, verifying and translating ENDF-6 formatted files
  ☆20Updated last month
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆61Updated 5 months ago
• openmc-data-storage / isotope-xs-plotter
  XSPlot - Neutron cross section plotter for isotopes
  ☆14Updated 2 years ago
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆32Updated 2 months ago
• KDSource / KDSource
  Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.
  ☆22Updated 4 months ago