Alternatives and similar repositories for GEOUNED

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

• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆27Updated 3 months ago
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated 3 weeks ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆48Updated this week
• pshriwise / xdg
  Accelerated Discretized Geometry
  ☆18Updated 3 weeks ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆44Updated 3 months ago
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated last month
• paulromano / endf-python
  Python ENDF Parser
  ☆35Updated 2 weeks ago
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆18Updated 9 months ago
• IAEA-NDS / open-benchmarks
  Computational inputs, reference outputs and experimental data for V&V systems
  ☆13Updated 4 months ago
• stellarmesh / stellarmesh
  Meshing library for nuclear workflows
  ☆50Updated 2 weeks ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆60Updated last week
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated this week
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆39Updated 3 months ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆39Updated 3 weeks ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆32Updated 2 months ago
• Open-Sn / opensn
  open-source Sn software
  ☆39Updated this week
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆114Updated 6 months ago
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆33Updated last month
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆48Updated last week
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 2 years ago
• KDSource / KDSource
  Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.
  ☆22Updated 3 months ago
• lanl / mcnptools
  ☆84Updated last year
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆32Updated 2 months ago
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆12Updated 3 months ago
• ukaea / SpaceClaim_API_NeutronicsTools
  Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis
  ☆14Updated 4 years 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…
  ☆158Updated last week
• fusion-energy / neutronics_material_maker
  A tool for making reproducible materials and standardizing use across several neutronics codes
  ☆24Updated 10 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆52Updated 2 weeks ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆115Updated 2 weeks ago