Alternatives and similar repositories for papillon-ndl:

Users that are interested in papillon-ndl are comparing it to the libraries listed below

• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆39Updated last month
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆39Updated this week
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆30Updated 2 months ago
• paulromano / endf-python
  Python ENDF Parser
  ☆31Updated 8 months ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆56Updated last month
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆18Updated last year
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆42Updated 2 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆51Updated last week
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆57Updated 2 months ago
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆29Updated 2 months ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆24Updated 7 months ago
• lanl / mcnptools
  ☆77Updated 10 months ago
• dassh-dev / dassh
  Ducted Assembly Steady State Heat Transfer Software (DASSH)
  ☆17Updated last year
• ezsolti / RFP
  ☆30Updated last month
• NuclearData / ACEFormat
  Format description for ACE nuclear data files
  ☆21Updated 2 years ago
• eepeterson / openmc_fusion_benchmarks
  ☆19Updated last week
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆104Updated last month
• 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 3 months ago
• njoy / NJOY21
  NJOY for the 21st Century
  ☆78Updated last year
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆40Updated this week
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆29Updated 7 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
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆17Updated 2 months ago
• njoy / ACEtk
  Toolkit for working with ACE-formatted data files
  ☆28Updated 2 weeks ago
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆52Updated 5 months ago
• mctools / mcpl
  Monte Carlo Particle Lists
  ☆30Updated this week
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆64Updated last year
• mctools / ncrystal
  NCrystal : a library for thermal neutron transport in crystals and other materials
  ☆44Updated this week
• toshihikokawano / DeCE
  ENDF-6 data interface and nuclear data evaluation assist code
  ☆15Updated last week
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆63Updated this week