A monte carlo pin cell spectral code for nuclear engineering applications.
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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. | |