Alternatives and similar repositories for aurora

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

• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated this week
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆66Updated 2 years ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆30Updated 7 months ago
• Open-Sn / opensn
  Open-source Sn software
  ☆54Updated this week
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆64Updated last month
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆35Updated 6 months ago
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 3 years ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆18Updated last month
• svalinn / parastell
  Parametric 3-D modeling toolset for stellarator fusion devices
  ☆38Updated last week
• neams-th-coe / cardinal
  High-Fidelity Multiphysics
  ☆122Updated this week
• xdg-org / xdg
  Accelerated Discretized Geometry
  ☆22Updated last month
• AnderGray / openmc_uq_sinbad
  Repository for running SINBAD benchmarks with OpenMC and UQ
  ☆10Updated 3 years ago
• paulromano / endf-python
  Python ENDF Parser
  ☆39Updated 2 months ago
• fusion-energy / neutronics_material_maker
  A tool for making reproducible materials and standardizing use across several neutronics codes
  ☆25Updated last year
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆55Updated last week
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆33Updated 6 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
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆20Updated last year
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆58Updated 4 months ago
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆14Updated 8 months ago
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆119Updated 11 months ago
• ezsolti / RFP
  ☆33Updated 5 months 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
• dassh-dev / dassh
  Ducted Assembly Steady State Heat Transfer Software (DASSH)
  ☆21Updated 6 months ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆34Updated this week
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆38Updated 3 weeks ago
• fusion-energy / openmc-plasma-source
  Creates a plasma source as an openmc.source object from input parameters that describe the plasma
  ☆39Updated 6 months ago
• KDSource / KDSource
  Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.
  ☆24Updated this week
• idaholab / virtual_test_bed
  The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository
  ☆63Updated this week
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆84Updated last month