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

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

Research output: Contribution to journalArticle

2 Citations (Scopus)

Abstract

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
Volume25
Issue number1-3
Publication statusPublished - 01-1998

Fingerprint

Fission products
cross section
Breeder reactors
product

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Waste Management and Disposal

Cite this

Devan, K. ; Gopalakrishnan, V. ; Mohanakrishnan, P. ; Sridharan, M. S. / Preparation of multigroup lumped fission product cross-sections from ENDF/B-VI for FBRs. In: Annals of Nuclear Energy. 1998 ; Vol. 25, No. 1-3. pp. 161-179.
@article{63f8f3a608d0425f98f85a8945e92649,
title = "Preparation of multigroup lumped fission product cross-sections from ENDF/B-VI for FBRs",
abstract = "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.",
author = "K. Devan and V. Gopalakrishnan and P. Mohanakrishnan and Sridharan, {M. S.}",
year = "1998",
month = "1",
language = "English",
volume = "25",
pages = "161--179",
journal = "Annals of Nuclear Energy",
issn = "0306-4549",
publisher = "Elsevier Limited",
number = "1-3",

}

Preparation of multigroup lumped fission product cross-sections from ENDF/B-VI for FBRs. / Devan, K.; Gopalakrishnan, V.; Mohanakrishnan, P.; Sridharan, M. S.

In: Annals of Nuclear Energy, Vol. 25, No. 1-3, 01.1998, p. 161-179.

Research output: Contribution to journalArticle

TY - JOUR

T1 - Preparation of multigroup lumped fission product cross-sections from ENDF/B-VI for FBRs

AU - Devan, K.

AU - Gopalakrishnan, V.

AU - Mohanakrishnan, P.

AU - Sridharan, M. S.

PY - 1998/1

Y1 - 1998/1

N2 - 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.

AB - 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.

UR - http://www.scopus.com/inward/record.url?scp=0031653875&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=0031653875&partnerID=8YFLogxK

M3 - Article

VL - 25

SP - 161

EP - 179

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

SN - 0306-4549

IS - 1-3

ER -