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 selected fission products that account for almost complete capture of fission products 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 and ABBN, are discussed.
|Number of pages||19|
|Journal||Annals of Nuclear Energy|
|Publication status||Published - 01-1998|
All Science Journal Classification (ASJC) codes
- Nuclear Energy and Engineering
- Waste Management and Disposal