IRDF-2002 Dosimetry Cross Section Processing in the BUGLE-96 (47 n) Neutron Group Structure Using Flat and Updated Problem Dependent Neutron Spectra

The whole set of the dosimetry point-wise cross sections of the International Reactor Dosimetry File IRDF-2002 were processed in the 47 neutron group structure of the ORNL BUGLE-96 broad-group cross section working library for LWR shielding applications through the GROUPIE program of the PREPRO 2007 nuclear data processing system. The reported 47 energy group response functions were calculated for all the following weighting spectrum conditions: • flat weighting spectrum; • 1/4 T (T = LWR pressure vessel thickness) pressure vessel weighting spectrum obtained from transport calculations using cross sections based on the JEFF-3.1.1 evaluated nuclear data library and processed with the NJOY-99.259 nuclear data processing system; • 1/4 T pressure vessel weighting spectrum obtained from transport calculations using cross sections based on the ENDF/B- VII.0 evaluated nuclear data library and processed with the NJOY -99.259 nuclear data processing system.