Discover fusion-energy/neutronics-workshop Open Source project

Stars
115
Rank 305,916 (Top 7 %)
Language
Jupyter Notebook
License
MIT License
Created over 3 years ago
Updated 5 months ago

fusion-energy

There are no reviews yet. Be the first to send feedback to the community and the maintainers!

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

paramak

Create parametric 3D fusion reactor CAD and neutronics models

Python

openmc-plasma-source

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

Python

neutronics_material_maker

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

Python

cad_to_dagmc

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

Python

fusion_neutronics_workflow

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

Python

magnetic_fusion_openmc_dagmc_paramak_example

Python

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

Python

openmc_source_plotter

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

Python

model_benchmark_zoo

A collection of neutronics models for comparing neutronics simulations in both CAD and CSG formats.

Python

plasmaboundaries

Determine plasma flux functions for various plasma parameters and plasma configurations.

Python

openmc_plot

A Python package that plots OpenMC geometry using web based technologies

Python

openmc_regular_mesh_plotter

A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.

Python

openmc-dagmc-wrapper

A Python package that extends OpenMC base classes to provide convenience features and standardized tallies when simulating DAGMC geometry with OpenMC.

Python

openmc_geometry_plot

Create axis slice plots of OpenMC geomtry with specified zoom

Python

openmc_tally_unit_converter

A Python package that finds and converts OpenMC tally units.

Python

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

Python

openmc_cylindrical_mesh_plotter

Plots slices of openmc cylindrical mesh tallies results

Python

openmc_depletion_plotter

Plot the isotopes present during depletion steps.

Python

paramak-cloud

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

HTML

dagmc_geometry_slice_plotter

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

Python

spectrum_plotter

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

Python

stl_to_h5m

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

Python

vertices_to_h5m

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

Python

openmc_cell_segmenter

Segments cells into smaller cells. Useful for redefining geometry for cell based shutdown dose rate simulations.

Python

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

Python

brep_to_h5m

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

Python

spline_replacer

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

Python

fusion-energy/neutronics-workshop

fusion-energy

Reviews

Repository Details

More Repositories