Alternatives and similar repositories for helios

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

• weft / warp
  continuous energy monte carlo neutron transport in general geometries on GPUs
  ☆46Updated 8 years ago
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆38Updated last month
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆22Updated 2 years ago
• openmc-dev / validation
  Collection of validation scripts, notebooks, results
  ☆11Updated last month
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆55Updated 3 months ago
• fispact / actigamma
  The package for producing gamma spec from nuclide activities
  ☆12Updated last year
• FRENSIE / FRENSIE
  Framework for REsearch in Nuclear ScIence and Engineering
  ☆15Updated 4 years ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆41Updated this week
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆66Updated 2 years ago
• Ahmed-Naceur / dragon5
  Three-Dimensional Discrete Ordinates Neutron, Photon, Electron and Positron Transport Code
  ☆11Updated 3 years ago
• hightower8083 / synchrad
  Synchrotron Radiation calculator via openCL
  ☆25Updated last month
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆55Updated last week
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆120Updated 11 months ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆52Updated last month
• mctools / ncrystal
  NCrystal : a library for thermal neutron transport in crystals and other materials
  ☆47Updated this week
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆43Updated last year
• mctools / mcpl
  Monte Carlo Particle Lists
  ☆35Updated this week
• 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…
  ☆42Updated last year
• SlaybaughLab / BART
  A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.
  ☆28Updated 4 years ago
• openmc-dev / openmc-notebooks
  Example Jupyter notebooks for OpenMC
  ☆41Updated 11 months ago
• njoy / ACEtk
  Toolkit for working with ACE-formatted data files
  ☆31Updated 3 weeks ago
• lanl / mcnptools
  ☆87Updated last year
• chi-tech / chi-tech
  Large scale scientific simulation engine
  ☆38Updated 2 years ago
• svalinn / ALARA
  Simulation of transmutation and decay in nuclear systems
  ☆34Updated this week
• NuclearData / ACEFormat
  Format description for ACE nuclear data files
  ☆22Updated 3 years ago
• njoy / NJOY21
  NJOY for the 21st Century
  ☆84Updated 2 years ago
• radioactivedecay / radioactivedecay
  A Python package for radioactive decay modelling that supports 1252 radionuclides, decay chains, branching, and metastable states.
  ☆111Updated 11 months ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆123Updated last week
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆41Updated 4 years ago
• fusion-energy / openmc_source_plotter
  A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles
  ☆12Updated last year