Transport Analysis of Several Cross-Section Libraries Used for Reactor Pressure Vessel Fluence Calculations

Several neutron cross-section libraries used for fluence calculations at the reactor pressure vessel (RPV) based on one-dimensional S_N transport calculations are analyzed. It is demonstrated that the BUGLE-80, SAILOR, and ELXSIR libraries yield similar results, while the CASK library predicts significantly different results through and beyond the RPV. The use of the revised ENDF/B- V iron cross sections yields a significant increase in the neutron fluxes beyond the ironcontaining regions. This result has direct impact on the reactor cavity dosimetry that is being considered for the RPV fluence estimation.