Alternatives and similar repositories for opendeplete:

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

• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆17Updated 4 months ago
• openmc-dev / validation
  Collection of validation scripts, notebooks, results
  ☆11Updated last year
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆29Updated last year
• EL-Bakkali-Jaafar / ERSN-OpenMC
  ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Ba…
  ☆13Updated 7 years ago
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆25Updated 4 months ago
• svalinn / Cubit-plugin
  Plugins and command extensions for Coreform Cubit
  ☆18Updated 7 months ago
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆50Updated 3 months ago
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆10Updated 2 years ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆49Updated last week
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated last year
• eepeterson / openmc_fusion_benchmarks
  ☆18Updated 5 months ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆22Updated 4 months ago
• svalinn / ALARA
  Simulation of transmutation and decay in nuclear systems
  ☆27Updated this week
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆35Updated 2 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆54Updated last month
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆37Updated 3 weeks ago
• mit-crpg / openmc-workshop
  Contains slides and example problems for OpenMC workshops and presentations
  ☆23Updated 2 years ago
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆16Updated last year
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆39Updated 6 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
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆26Updated last week
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆64Updated last year
• Open-Sn / opensn
  open-source Sn software
  ☆25Updated this week
• fispact / pypact
  A Python package for parsing FISPACT-II output
  ☆26Updated 10 months ago
• 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 last month
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆38Updated 3 weeks ago
• openmc-data-storage / isotope-xs-plotter
  XSPlot - Neutron cross section plotter for isotopes
  ☆14Updated last year
• SlaybaughLab / BART
  A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.
  ☆25Updated 3 years ago
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆11Updated 8 months ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆36Updated last year