fusion-energy/vertices_to_h5m

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Python
License
MIT License
Created over 2 years ago
Updated over 1 year ago

fusion-energy/vertices_to_h5m

fusion-energy

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Converts mesh vertices and connectivity to h5m geometry files compatible with DAGMC simulations

neutronics-workshop

A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools

Jupyter Notebook

paramak

Create parametric 3D fusion reactor CAD and neutronics models

openmc-plasma-source

Creates a plasma source as an openmc.source object from input parameters that describe the plasma

neutronics_material_maker

A tool for making reproducible materials and standardizing use across several neutronics codes

cad_to_dagmc

Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files

fusion_neutronics_workflow

Combines open source packages to produce an automated fusion specific neutronics workflow

magnetic_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 API

openmc_source_plotter

A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles

model_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 technologies

openmc_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 zoom

openmc_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 OpenMC

openmc_cylindrical_mesh_plotter

Plots slices of openmc cylindrical mesh tallies results

openmc_depletion_plotter

Plot the isotopes present during depletion steps.

paramak-cloud

About A cloud based version of the paramak for making models in the browser

dagmc_geometry_slice_plotter

A minimal Python package that produces slice plots through h5m DAGMC geometry files

spectrum_plotter

A Python package for creating publication quality plots for neutron / photon / particle spectrum

stl_to_h5m

Convert non overlapping STL files into a DAGMC h5m file complete with material tags and ready for use in neutronics simulations.

openmc_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 workshop

dagmc_h5m_file_inspector

Extracts information from DAGMC h5m files including volumes number, material tags

brep_to_h5m

Converts Brep CAD geometry files to h5m geometry files compatible with DAGMC simulations

spline_replacer

Replaces splines in CAD files with a series of straight edges to allow CAD geometry to be converted to CSG geometry.