Towards On-The-Fly Dose Analysis using the Shift Monte Carlo Code

This summary presents a radiation dose calculation
methodology that allows on-the-fly dose evaluation of a system with different radiation sources. The methodology uses a
radiation tally that is binned by the particle birth energy and
spatial region. This methodology adjusts the binned tally by the
actual source strength of each energy group and source region
to obtain the final dose rates for a problem of interest. The
binned tallies are generated one time using a computationally
expensive Monte Carlo (MC) radiation transport calculation
with a user-defined source spectra and then combined with the
actual radiation source spectra for a problem of interest using
post processing. This method reduces the number of computationally expensive shielding calculations required to evaluate
the dose of a single system loaded with various combinations
of radiation sources. This has been implemented in the Shift
Monte Carlo code [1] and used for analyzing a spent nuclear
fuel (SNF) storage cask. A reference calculation that includes
the actual radiation source strengths during the radiation transport analysis is used to verify the method.