46 projects
cad-to-dagmc
Converts CAD files to a DAGMC h5m file
yamc
Yet Another Monte Carlo — neutron transport with mesh geometry support
cad-to-dagmc-mesher
CDT surface mesher with DAG scheduler for DAGMC geometry
rad-point-kernel
Point-kernel neutron and photon transmission/dose calculator
rad-point-kernel-core
Point-kernel neutron and photon transmission/dose calculator (compiled core)
nuclear-data-to-yamc-format
Export OpenMC nuclear data objects to Apache Arrow IPC format
geouned
Conversion tool from CAD to CGS/CGS to CAD for Monte Carlo particle transport codes (OpenMC, Phits, Serpent, MCNP)
openmc-data
A Python package containing a collection of scripts for producing and downloading data for OpenMC
dagmc-h5m-file-inspector
Extracts information from DAGMC h5m files including volumes number, material tags
paramak
Create 3D fusion reactor CAD models based on input parameters
neutronics-material-maker
A tool for making reproducible materials and standardizing use across several neutronics codes
assembly-mesh-plugin
CadQuery plugin to create a mesh of an assembly with corresponding data
cadquery-direct-mesh-plugin
CadQuery plugin to go directly from a CadQuery assembly to a mesh without relying on external dependencies.
openmc-source-plotter
A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles.
openmc-geometry-plot
Plot OpenMC geometry, interactive or static 2D slice plots.
materials-for-mc
Material builder for Monte Carlo simulations
openmc-plasma-source
Creates tokamak and fusion point sources for OpenMC
hdf5-nuclear-data-reader
A package for reading nuclear data from HDF5 files in the OpenMC format
openmc-depletion-plotter
Plot the isotopes present during depletion steps.
openmc-data-downloader
A tool for selectively downloading h5 files for specified isotopes / elements from your libraries of choice
example-python-package-with-rust-backend
None
openmc-plot
A Python package containing a collection of scripts for producing and downloading data for OpenMC
openmc-regular-mesh-plotter
A Python package for creating plots of OpenMC regular mesh tallies with the underlying geometry
openmc-cylindrical-mesh-plotter
A Python package for creating plots of OpenMC cylindrical mesh tallies
openmc-cell-segmenter
todo
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
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
does-it-fit
A python package that checks if shapes positioned on the circumference of a circle overlap or not
cad-to-h5m
Converts CAD files to a DAGMC h5m file using Cubit
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
openmc-dagmc-wrapper
Perform a set of standard neutronics simulations with OpenMC and DAGMC
openmc-data-to-json
A tool for selectively extracting cross sections from OpenMC h5 files.
plasmaboundaries
Determine plasma flux functions for various plasma parameters and plasma configurations
remove-dagmc-tags
A tool for selectively removing tags such as the graveyard from DAGMC h5m files.
parametric-plasma-source
Parametric plasma source for fusion simulations in OpenMC
csg2csg
Convert CSG geometry into different formats
breeder-blanket-model-maker
Input blanket envelopes and retrive detailed blanket geometry
