| 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. | |