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
  ☆39Updated last month
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated this week
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆17Updated this week
• toshihikokawano / DeCE
  ENDF-6 data interface and nuclear data evaluation assist code
  ☆16Updated 7 months ago
• AnderGray / openmc_uq_sinbad
  Repository for running SINBAD benchmarks with OpenMC and UQ
  ☆10Updated 3 years ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆34Updated this week
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 3 years ago
• jlball / arc-nonproliferation
  An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.
  ☆11Updated last year
• IRFM / divHretention
  Tool to estimate H retention in tokamak divertors
  ☆10Updated 4 years ago
• xdg-org / xdg
  Accelerated Discretized Geometry
  ☆19Updated last week
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆14Updated 7 months ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆30Updated 6 months ago
• fispact / pypact
  A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact
  ☆32Updated 2 weeks ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆53Updated 2 months ago
• IAEA-NDS / endf-parserpy
  Python package for reading, writing, verifying and translating ENDF-6 formatted files
  ☆22Updated 4 months ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆41Updated 4 years ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆48Updated this week
• njoy / NJOY21
  NJOY for the 21st Century
  ☆84Updated last year
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated last month
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆61Updated 2 months ago
• fusion-energy / cad_to_h5m
  Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API
  ☆11Updated 2 years ago
• Open-Sn / opensn
  Open-source Sn software
  ☆52Updated this week
• ezsolti / RFP
  ☆33Updated 4 months ago
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆20Updated last year
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆32Updated last month
• openmc-data-storage / openmc_data_downloader
  A Python package for downloading h5 cross section files for use in OpenMC.
  ☆14Updated 11 months ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆81Updated this week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆52Updated last week
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆40Updated 3 weeks ago
• ukaea / neutronics_material_maker
  A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak
  ☆19Updated 4 years ago