Alternatives and similar repositories for saltproc:

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

• svalinn / ALARA
  Simulation of transmutation and decay in nuclear systems
  ☆28Updated 2 months ago
• arfc / moltres
  Repository for Moltres, a code for simulating Molten Salt Reactors
  ☆67Updated 3 weeks ago
• openmsr / msre
  detailed cad model of the msre
  ☆36Updated last month
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆42Updated 2 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
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆51Updated last week
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆29Updated 7 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆57Updated 2 months ago
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆32Updated 3 weeks ago
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆109Updated last month
• KDSource / KDSource
  Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.
  ☆20Updated 5 months ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆40Updated 9 months ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆40Updated this week
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆24Updated 7 months ago
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆30Updated 2 months ago
• imronuke / ADPRES
  An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool
  ☆23Updated 4 years ago
• FRENSIE / FRENSIE
  Framework for REsearch in Nuclear ScIence and Engineering
  ☆14Updated 3 years ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆33Updated last week
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆36Updated last year
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆64Updated last year
• tarekbardouni / ERSN-OpenMC
  ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Ba…
  ☆29Updated 9 months ago
• fusion-energy / neutronics_material_maker
  A tool for making reproducible materials and standardizing use across several neutronics codes
  ☆23Updated 6 months ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated 2 months ago
• mctools / mcpl
  Monte Carlo Particle Lists
  ☆30Updated this week
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated last year
• NuclearData / ACEFormat
  Format description for ACE nuclear data files
  ☆21Updated 2 years ago
• anl-rtr / adder
  The Advanced Dimensional Depletion for Engineering of Reactors (ADDER) Software
  ☆15Updated 8 months ago
• lanl / CGMF
  CGMF nuclear fission fragment de-excitation statistical code
  ☆25Updated last year
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• eepeterson / openmc_fusion_benchmarks
  ☆19Updated last week