Alternatives and similar repositories for Cubit-plugin

Users that are interested in Cubit-plugin are comparing it to the libraries listed below

• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆24Updated last year
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆38Updated last month
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆58Updated 4 months ago
• openmc-dev / validation
  Collection of validation scripts, notebooks, results
  ☆11Updated last month
• Open-Sn / opensn
  Open-source Sn software
  ☆58Updated this week
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆66Updated 2 years ago
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆120Updated 11 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆64Updated last week
• ukaea / neutronics_material_maker
  A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak
  ☆19Updated 4 years ago
• fusion-energy / openmc-plasma-source
  Creates a plasma source as an openmc.source object from input parameters that describe the plasma
  ☆39Updated 7 months ago
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆38Updated 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
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆40Updated 8 months ago
• llnl / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆32Updated last week
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆43Updated last year
• openmc-data-storage / isotope-xs-plotter
  XSPlot - Neutron cross section plotter for isotopes
  ☆14Updated 2 years ago
• SlaybaughLab / BART
  A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.
  ☆28Updated 4 years ago
• paulromano / endf-python
  Python ENDF Parser
  ☆39Updated last week
• AnderGray / openmc_uq_sinbad
  Repository for running SINBAD benchmarks with OpenMC and UQ
  ☆10Updated 3 years ago
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated 3 weeks ago
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated 2 years ago
• Thea-Energy / stellarvista
  3D visualizations for DAGMC & OpenMC
  ☆14Updated last month
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 3 years ago
• CEMeNT-PSAAP / MCDC
  MC/DC: Monte Carlo Dynamic Code
  ☆50Updated last week
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆85Updated 2 months ago
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆20Updated last year
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆33Updated 7 months ago
• ERMETE-Lab / MP-OFELIA
  Openmc-FEnicsx for muLtiphysics tutorIAl
  ☆16Updated 8 months ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆55Updated 2 weeks ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆55Updated 4 months ago