27 projects
openmc-geometry-plot
Plot OpenMC geometry, interactive or static 2D slice plots.
cad-to-dagmc
Converts CAD files to a DAGMC h5m file
openmc-plasma-source
Creates tokamak and ICF plasma sources for OpenMC
openmc-cylindrical-mesh-plotter
A Python package for creating plots of OpenMC cylindrical mesh tallies
openmc-source-plotter
A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles.
openmc-regular-mesh-plotter
A Python package for creating plots of OpenMC regular mesh tallies with the underlying geometry
openmc-cell-segmenter
todo
neutronics-material-maker
A tool for making reproducible materials and standardizing use across several neutronics codes
openmc-depletion-plotter
Plot the isotopes present during depletion steps.
openmc-plot
A Python package containing a collection of scripts for producing and downloading data for OpenMC
openmc-data-downloader
A tool for selectively downloading h5 files for specified isotopes / elements from your libraries of choice
dagmc-geometry-slice-plotter
A minimal Python package for creating plots of slices through DAGMC geometry
regular-mesh-plotter
A Python package for creating publication quality plots of regular mesh tallies with the underlying geometry
paramak
Create 3D fusion reactor CAD models based on input parameters
brep-part-finder
A Python package to identify the part ID number in Brep format CAD files
stl-to-h5m
Converts STL files to a DAGMC h5m file using PyMoab
brep-to-h5m
Converts Brep CAD geometry files to h5m geometry files compatible with DAGMC simulations
vertices-to-h5m
Converts mesh vertices and connectivity to h5m geometry files compatible with DAGMC simulations
dagmc-bounding-box
Find the bounding box and other related properties of a DAGMC h5m file
openmc-track-file-processor
Create 3D fusion reactor CAD models based on input parameters
spectrum-plotter
A Python package for creating publication quality plots for neutron / photon / particle spectrum
openmc-mesh-tally-to-vtk
A Python package for converting OpenMC mesh tallies to VTK files and optionally converting the units
openmc-tally-unit-converter
Convert OpenMC tallies into user friendly units
lithium-enrichment-cost-calculator
Create 3D fusion reactor CAD models based on input parameters
plasmaboundaries
Determine plasma flux functions for various plasma parameters and plasma configurations
parametric-plasma-source
Parametric plasma source for fusion simulations in OpenMC
csg2csg
Convert CSG geometry into different formats
