task_07_CSG_cell_tally_spectra

Task 7 - Neutron and photon spectra

Please allow 15 minutes for this task.

Expected outputs from this task are also in the presentation.

In this task you will use OpenMC to tally neutron and photon spectra on different surfaces and cells in a geometry.

Learning Outcomes

Plotting neutron / photon spectra for cells and surfaces and observing the changing neutron energy at different locations in the reactor.
Performing coupled neutron photon simulations where photons are created from neutron interactions.

Name		Name	Last commit message	Last commit date
parent directory ..
1_example_neutron_flux_and_units.ipynb		1_example_neutron_flux_and_units.ipynb
2_example_neutron_spectra_on_cell.ipynb		2_example_neutron_spectra_on_cell.ipynb
3_example_neutron_spectra_on_surface.ipynb		3_example_neutron_spectra_on_surface.ipynb
4_example_photon_spectra.ipynb		4_example_photon_spectra.ipynb
5_neutron_energy_loss_plot.ipynb		5_neutron_energy_loss_plot.ipynb
README.md		README.md