Preparation of multigroup lumped fission product cross-sections from ENDF/B-VI for FBRs

K. Devan, V. Gopalakrishnan, P. Mohanakrishnan, M. S. Sridharan

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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.

Original languageEnglish
Pages (from-to)161-179
Number of pages19
JournalAnnals of Nuclear Energy
Issue number1-3
Publication statusPublished - 01-1998


All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Waste Management and Disposal

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