Pinned Repositories
cad_to_dagmc
Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files
cad_to_h5m
Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API
fusion_neutronics_workflow
Combines open source packages to produce an automated fusion specific neutronics workflow
magnetic_fusion_openmc_dagmc_paramak_example
neutronics-workshop
A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
neutronics_material_maker
A tool for making reproducible materials and standardizing use across several neutronics codes
openmc-plasma-source
Creates a plasma source as an openmc.source object from input parameters that describe the plasma
openmc_regular_mesh_plotter
A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
openmc_source_plotter
A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles
paramak
Create parametric 3D fusion reactor CAD and neutronics models
Fusion Energy's Repositories
fusion-energy/neutronics-workshop
A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
fusion-energy/paramak
Create parametric 3D fusion reactor CAD and neutronics models
fusion-energy/openmc-plasma-source
Creates a plasma source as an openmc.source object from input parameters that describe the plasma
fusion-energy/cad_to_dagmc
Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files
fusion-energy/neutronics_material_maker
A tool for making reproducible materials and standardizing use across several neutronics codes
fusion-energy/cad_to_h5m
Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API
fusion-energy/magnetic_fusion_openmc_dagmc_paramak_example
fusion-energy/openmc_regular_mesh_plotter
A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
fusion-energy/openmc_source_plotter
A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles
fusion-energy/model_benchmark_zoo
A collection of neutronics models for comparing neutronics simulations in both CAD and CSG formats.
fusion-energy/openmc-dagmc-wrapper
A Python package that extends OpenMC base classes to provide convenience features and standardized tallies when simulating DAGMC geometry with OpenMC.
fusion-energy/openmc_plot
A Python package that plots OpenMC geometry using web based technologies
fusion-energy/inertial_fusion_openmc_dagmc_paramak_example
A minimal example implementation of an open source method of making DAGMC geometry with Paramak and simulating tritium production with OpenMC
fusion-energy/openmc_geometry_plot
Create axis slice plots of OpenMC geomtry with specified zoom
fusion-energy/openmc_cylindrical_mesh_plotter
Plots slices of openmc cylindrical mesh tallies results
fusion-energy/dagmc_geometry_slice_plotter
A minimal Python package that produces slice plots through h5m DAGMC geometry files
fusion-energy/openmc_depletion_plotter
Plot the isotopes present during depletion steps.
fusion-energy/vertices_to_h5m
Converts mesh vertices and connectivity to h5m geometry files compatible with DAGMC simulations
fusion-energy/openmc_cell_segmenter
Segments cells into smaller cells. Useful for redefining geometry for cell based shutdown dose rate simulations.
fusion-energy/spline_replacer
Replaces splines in CAD files with a series of straight edges to allow CAD geometry to be converted to CSG geometry.
fusion-energy/brep_to_h5m
Converts Brep CAD geometry files to h5m geometry files compatible with DAGMC simulations
fusion-energy/dagmc_h5m_file_inspector
Extracts information from DAGMC h5m files including volumes number, material tags
fusion-energy/neutronics-workshop-slides
The accompanying for the neutronics workshop
fusion-energy/brep_part_finder
A Python package to identify the part ID number in Brep format CAD files
fusion-energy/fusion-neutronics-presentation-slides
An open source slide deck on fusion neutronics
fusion-energy/fusion_activation_handbook
Code for automated production of a fusion materials activation handbook using OpenMC. Containing simulated activity, dose and decay heat characteristics for elements and materials exposed to neutron irradiation.
fusion-energy/openmc_csg_slice_plotter
Plots slices of OpenMC native GSC surface geometry with hovertext surface identification
fusion-energy/openmc_mesh_tally_to_vtk
A Python package for converting OpenMC mesh tallies to VTK files and optionally converting the units
fusion-energy/openmc_weight_window_generator
Generate weight windows for use in OpenMC simulation with varience reduction
fusion-energy/step_to_h5m
This repo has moved to https://github.com/fusion-energy/cad_to_dagmc