|
A monte carlo pin cell spectral code for nuclear engineering applications.
|
Namespaces | |
| pinspec.plotter | |
| The plotter module provides utility functions to plot data from PINSPEC's C++ classes, in particular, tally data and cross-sections, thermal scattering PDFs/CDFs, etc. | |
Functions | |
| def | pinspec.plotter.plotMicroXS |
| Plots the microscopoic cross-section(s) for one or more reaction rates for an isotope. More... | |
| def | pinspec.plotter.plotMacroXS |
| Plots the macroscopic cross-section(s) for one or more reaction rates for a material. More... | |
| def | pinspec.plotter.plotFlux |
| Plots one or more flux tallies by energy. More... | |
| def | pinspec.plotter.plotThermalScattering |
| Plots the thermal scattering PDFs and CDFs for an isotope. More... | |
| def | pinspec.plotter.plotFissionSpectrum |
| Plots the fission spectrum PDF and CDF. More... | |
| def | pinspec.plotter.plotRI |
| Plots a resonance integral (RIEff or RITrue) as a step function. More... | |
| def | pinspec.plotter.plotGroupXS |
| Plots a multi-group cross-section as a step function. More... | |
| def | pinspec.plotter.plotSlice |
| This method takes in a region or a geometry object and plots a color-coded 2D surface plot representing a planar slice through the space. More... | |
| def | pinspec.plotter.plotFissionSourceDist |
| Plots a vector field of the fission site source distribution. More... | |
| def | pinspec.plotter.trackANeutron |
| This method takes in a geometry class object and tracks a neutron as it travels across the geomgetry. More... | |
Variables | |
| int | pinspec.plotter.flux_plot_num = 0 |
| A static variable to auto-generate unique filenames for flux plots. | |
| string | pinspec.plotter.subdirectory = "/plots/" |
| A static variable for the output directory in which to save plots. | |