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Repositories (4)
neutronics-workshop
fusion-energy/neutronics-workshop
Jupyter Notebook
A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
203
70
neutronics_material_maker
fusion-energy/neutronics_material_maker
Python
A tool for making reproducible materials and standardizing use across several neutronics codes
28
16
openmc_depletion_plotter
fusion-energy/openmc_depletion_plotter
Python
Plot the isotopes present during depletion steps.
12
3
rad_point_kernel
fusion-energy/rad_point_kernel
Python
A point kernel code for neutron and photon shielding calculations including buildup factor calculation and Gaussian Processes fitting
3
3