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Angular flux tallying capabilities for Random Ray #4071

Description

@j-fletcher

Description

Currently, only tallies based on the scalar flux are possible in Random Ray mode. Beyond the tallies themselves, the ability to output angular flux information will enable automated source biasing over angle--in addition to space and energy--as part of the FW-CADIS workflow. Additionally, accumulating the batch-wise angular flux in each source region is a necessary precursor to computing anisotropic scattering source terms.

Compatibility

As the reduction in memory overhead from not storing angular fluxes at the boundary is one of the key advantages of Random Ray over conventional MOC, care should be taken that in storing and tallying potentially $N_\Omega$ flux values in $N_E$ energy bins in $N_{SR}$ source regions we do not erase most if not all of those gains. Likewise, anisotropic scattering sources could potentially require storing a significant amount of groupwise angular data in each source region of the geometry.

However, if the scope is limited to simply tallying the angular flux in certain regions of phase space, the groupwise angular flux could easily be banked in a select number of source regions by simply adding a new vector in each region to which each passing ray contributes delta_psi_, in the same way as is done with scalar_flux_new_. Additional changes will be needed to SourceRegion to indicate when a given region is in the area of interest where angular flux will be tallied, and to the TallyTask class to indicate when a specific tally score is based on the angular flux instead of the scalar flux. Finally, while tally scores are currently updated at the end of each batch, "live" RandomRay instances will need a method to determine which angular bin to accumulate to during transport. Therefore, the angular binning structure defined on such a tally will likely need to be shared by FlatSourceDomain and dictate the size of the "scalar_flux_new_" analogue mentioned earlier.

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