Alternatives and similar repositories for serpent-tools:

Users that are interested in serpent-tools are comparing it to the libraries listed below

• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆37Updated 3 weeks ago
• paulromano / endf-python
  Python ENDF Parser
  ☆27Updated 5 months ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆38Updated 3 weeks ago
• njoy / NJOY21
  NJOY for the 21st Century
  ☆75Updated 11 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆54Updated last month
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆22Updated 4 months ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆99Updated 2 months ago
• ezsolti / RFP
  ☆29Updated 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
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆33Updated 2 weeks ago
• openmsr / msr-archive
  curated documents pertaining to early molten salt reactor research.
  ☆21Updated 10 months ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆36Updated last year
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆59Updated 3 weeks ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆13Updated 7 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆49Updated last week
• dassh-dev / dassh
  Ducted Assembly Steady State Heat Transfer Software (DASSH)
  ☆17Updated last year
• fusion-energy / neutronics-workshop
  A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…
  ☆130Updated this week
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆105Updated last week
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆25Updated 4 months ago
• highness-eu / NJOY-NCrystal-Library
  Thermal Scattering Library created with NJOY+NCrystal
  ☆9Updated 2 years ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆34Updated this week
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆25Updated 3 weeks 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
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆64Updated last year
• eepeterson / openmc_fusion_benchmarks
  ☆18Updated 5 months ago
• mit-crpg / openmc-reactor-examples
  Catalogs a plethora of reactor inputs for OpenMC
  ☆19Updated 3 years ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆39Updated 6 months ago
• lanl / mcnptools
  ☆71Updated 7 months ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆35Updated 2 months ago
• mctools / mcpl
  Monte Carlo Particle Lists
  ☆30Updated 10 months ago