neutronics-workshop
A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics toolsparamak
Create parametric 3D fusion reactor CAD and neutronics modelsopenmc-plasma-source
Creates a plasma source as an openmc.source object from input parameters that describe the plasmaneutronics_material_maker
A tool for making reproducible materials and standardizing use across several neutronics codescad_to_dagmc
Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m filesfusion_neutronics_workflow
Combines open source packages to produce an automated fusion specific neutronics workflowmagnetic_fusion_openmc_dagmc_paramak_example
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 APIopenmc_source_plotter
A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particlesmodel_benchmark_zoo
A collection of neutronics models for comparing neutronics simulations in both CAD and CSG formats.plasmaboundaries
Determine plasma flux functions for various plasma parameters and plasma configurations.openmc_plot
A Python package that plots OpenMC geometry using web based technologiesopenmc_regular_mesh_plotter
A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.openmc-dagmc-wrapper
A Python package that extends OpenMC base classes to provide convenience features and standardized tallies when simulating DAGMC geometry with OpenMC.openmc_geometry_plot
Create axis slice plots of OpenMC geomtry with specified zoomopenmc_tally_unit_converter
A Python package that finds and converts OpenMC tally units.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 OpenMCopenmc_cylindrical_mesh_plotter
Plots slices of openmc cylindrical mesh tallies resultsopenmc_depletion_plotter
Plot the isotopes present during depletion steps.paramak-cloud
About A cloud based version of the paramak for making models in the browserdagmc_geometry_slice_plotter
A minimal Python package that produces slice plots through h5m DAGMC geometry filesspectrum_plotter
A Python package for creating publication quality plots for neutron / photon / particle spectrumstl_to_h5m
Convert non overlapping STL files into a DAGMC h5m file complete with material tags and ready for use in neutronics simulations.vertices_to_h5m
Converts mesh vertices and connectivity to h5m geometry files compatible with DAGMC simulationsopenmc_cell_segmenter
Segments cells into smaller cells. Useful for redefining geometry for cell based shutdown dose rate simulations.neutronics-workshop-slides-old
The accompanying for the neutronics workshopdagmc_h5m_file_inspector
Extracts information from DAGMC h5m files including volumes number, material tagsbrep_to_h5m
Converts Brep CAD geometry files to h5m geometry files compatible with DAGMC simulationsspline_replacer
Replaces splines in CAD files with a series of straight edges to allow CAD geometry to be converted to CSG geometry.Love Open Source and this site? Check out how you can help us