A monte carlo pin cell spectral code for nuclear engineering applications.
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plotter.py File Reference

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.