PREPARATION OF MULTIGROUP LUMPED FISSION PRODUCT CROSS-SECTIONS FROM ENDF/B-VI FOR FBRs

摘要

Multigroup pseudo fission product cross-sections were computed from the American evaluated nuclear data library ENDF/B-VI, corresponding to various burnups of the proposed 500 MWe prototype fast breeder reactor (PFBR), in India. The data were derived from the cross-sections of 111 selec- ted fission products that account for almost complete capture of fission pro- ducts in an FBR. The dependence of burnup on the pseudo fission product cross-sections, and comparison with other data sets, viz. JNDC, ENDF/B-IV land ABBN, are discussed.