Application of recent iron evaluations of ENDF/B, JEF and JENDL to neutron transport calculations through light water reactor pressure vessel

Abstract-It has been generally known that iron cross section sets derived from END FIB-IV and ENDF/B-V evaluations underestimate the transmission of fast neutrons through light water reactor pressure vessel. In recent years, ENDF/B, JEF and JENDL iron data have been newly revised. To verify an applicability of the new iron evaluations to neutron transport calculations through the pressure vessel, fast neutron spectra and various threshold dosimeter activities obtained with the revised iron data have been intercompared. The results calculated with ENDF/B-VI iron data among those show good agreements with the measurements. And as far as fast neutron dosimetry application of pressure vessels is concerned, the result of JEF-2.2 iron data is improved a little compared with that of JEF-l, and JENDL-3.2 iron data show more or less underpredicted result relative to earlier JENDL iron data.