Alternatives and similar repositories for dassh

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

• idaholab / virtual_test_bed
  The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository
  ☆63Updated this week
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆66Updated 2 years ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆55Updated last week
• ezsolti / RFP
  ☆33Updated 5 months ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆61Updated 3 months ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆40Updated 3 weeks ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆43Updated last year
• paulromano / endf-python
  Python ENDF Parser
  ☆39Updated 2 months ago
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated last week
• SlaybaughLab / BART
  A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.
  ☆28Updated 4 years ago
• neams-th-coe / cardinal
  High-Fidelity Multiphysics
  ☆122Updated this week
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated this week
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆30Updated 7 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆64Updated last month
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated 2 years ago
• anl-rtr / adder
  The Advanced Dimensional Depletion for Engineering of Reactors (ADDER) Software
  ☆20Updated last month
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆40Updated 7 months ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆41Updated 4 years ago
• xdg-org / xdg
  Accelerated Discretized Geometry
  ☆22Updated last month
• mohamedlahdour / OpenNTP
  In this project we develop an OpenNTP package to solve the multi-group neutron transport equation.
  ☆15Updated 5 years ago
• Ahmed-Naceur / dragon5
  Three-Dimensional Discrete Ordinates Neutron, Photon, Electron and Positron Transport Code
  ☆11Updated 3 years ago
• KDSource / KDSource
  Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.
  ☆24Updated this week
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆123Updated last week
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆20Updated last year
• 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
• Open-Sn / opensn
  Open-source Sn software
  ☆54Updated this week
• NuclearData / ACEFormat
  Format description for ACE nuclear data files
  ☆22Updated 3 years ago
• ERMETE-Lab / MP-OFELIA
  Openmc-FEnicsx for muLtiphysics tutorIAl
  ☆16Updated 7 months ago
• 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…
  ☆173Updated last week
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆33Updated 6 months ago