Fusion Energy

A collection of software projects related to fusion energy

Pinned Repositories

cad_to_dagmc
Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files
Language:Python24 2 256
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
Language:Python12 2 196
fusion_neutronics_workflow
Combines open source packages to produce an automated fusion specific neutronics workflow
Language:Python14 1 144
magnetic_fusion_openmc_dagmc_paramak_example
Language:Python13 1 56
neutronics-workshop
A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
Language:Jupyter Notebook127 6 6854
neutronics_material_maker
A tool for making reproducible materials and standardizing use across several neutronics codes
Language:Python21 2 711
openmc-plasma-source
Creates a plasma source as an openmc.source object from input parameters that describe the plasma
Language:Python31 3 3611
openmc_regular_mesh_plotter
A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
Language:Python11 1 171
paramak
Create parametric 3D fusion reactor CAD and neutronics models
Language:Python71 5 9822
plasmaboundaries
Determine plasma flux functions for various plasma parameters and plasma configurations.
Language:Python10 2 73

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
Language:Jupyter Notebook127 6 6854
fusion-energy/paramak
Create parametric 3D fusion reactor CAD and neutronics models
Language:Python71 5 9822
fusion-energy/openmc-plasma-source
Creates a plasma source as an openmc.source object from input parameters that describe the plasma
Language:Python31 3 3611
fusion-energy/cad_to_dagmc
Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files
Language:Python24 2 256
fusion-energy/neutronics_material_maker
A tool for making reproducible materials and standardizing use across several neutronics codes
Language:Python21 2 711
fusion-energy/magnetic_fusion_openmc_dagmc_paramak_example
Language:Python13 1 56
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
Language:Python12 2 196
fusion-energy/openmc_regular_mesh_plotter
A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
Language:Python11 1 171
fusion-energy/openmc_source_plotter
A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles
Language:Python10 1 103
fusion-energy/model_benchmark_zoo
A collection of neutronics models for comparing neutronics simulations in both CAD and CSG formats.
Language:Python8 1 33
fusion-energy/openmc_plot
A Python package that plots OpenMC geometry using web based technologies
Language:Python8 1 141
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.
Language:Python7 3 392
fusion-energy/openmc_cylindrical_mesh_plotter
Plots slices of openmc cylindrical mesh tallies results
Language:Python6 1 91
fusion-energy/openmc_geometry_plot
Create axis slice plots of OpenMC geomtry with specified zoom
Language:Python6 1 11
fusion-energy/openmc_depletion_plotter
Plot the isotopes present during depletion steps.
Language:Python5 3 22
fusion-energy/dagmc_geometry_slice_plotter
A minimal Python package that produces slice plots through h5m DAGMC geometry files
Language:Python4 1 71
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.
Language:Python4 1 1
fusion-energy/fusion_neutron_utils
Package for calculating the neutron energy, energy distribution and reactivity for neutrons from DT and DD fusion reactions
Language:Rust3
fusion-energy/vertices_to_h5m
Converts mesh vertices and connectivity to h5m geometry files compatible with DAGMC simulations
Language:Python3 1 42
fusion-energy/openmc_cell_segmenter
Segments cells into smaller cells. Useful for redefining geometry for cell based shutdown dose rate simulations.
Language:Python2 1 1
fusion-energy/brep_to_h5m
Converts Brep CAD geometry files to h5m geometry files compatible with DAGMC simulations
Language:Python1 1 92
fusion-energy/csg_surface_distance
A Rust Cargo crate for finding the distance between a point and a constructive solid geometry surface
Language:Rust1
fusion-energy/dagmc_h5m_file_inspector
Extracts information from DAGMC h5m files including volumes number, material tags
Language:Python1 1 21
fusion-energy/neutronics-workshop-slides
The accompanying for the neutronics workshop
Language:HTML1 1 1
fusion-energy/brep_part_finder
A Python package to identify the part ID number in Brep format CAD files
Language:Python1 4
fusion-energy/fusion-neutronics-presentation-slides
An open source slide deck on fusion neutronics
Language:HTML1 1
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.
Language:Python1 0
fusion-energy/openmc_mesh_tally_to_vtk
A Python package for converting OpenMC mesh tallies to VTK files and optionally converting the units
Language:Python1 2
fusion-energy/openmc_weight_window_generator
Generate weight windows for use in OpenMC simulation with varience reduction
Language:Python1 12
fusion-energy/step_to_h5m
This repo has moved to https://github.com/fusion-energy/cad_to_dagmc
1 0