INDC(IND)-35G - IAEA Nuclear Data Services

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Generation of Activation Cross Sections in the DLC 100
Group Structure for Structural Isotopes
(V.Gopalakrishnan, M.M.Ramanadhan, S.Ganesan)
Activation cross sections were required in the DLC
100 energy group structure for the computation of activation
rates in stainless steel of Intermediate heat exchangers in
fast reactor system. The program 'RKX1' was used to obtain
these cross sections using the data available with us in the
ENDF/B-TV format. ' The isotopes and the basic data library
from which they were retrieved are as follows: •
Mn 55 and Co 59 - ENDL 78 of LLL 2
Fe 5 \ Fe 56 , Fe 58 ,Cr 5 °)
58 60 6h \ JENDL1 of Japan
In addition to the activation cross sections viz. 0 ( n »p)
(j (n.^jF), 100 group cross sections have also been generated
for other neutron nuclear reactions for which basic data are
available with us. These group cross sections have been saved
on magnetic tape and can be made available to interested users
on request.
1. V.Gopalakrishnan and S.Ganesan 'A Note on the program REX1
for Accurate Generation of Infinite Dilution Cross
Sections, Elastic and Inelastic Transfer Matrices for
Fast Reactor Applications', Internal note REDG/RP-243
(Sept. 1983).
2. 0. Schwerer, ENDF-78 LLL Evaluated Nuclear Data Library
1978, IAEA-NDS-11 (1979), Vienna.
3. N.DayDay, JENDL-1 Japanese Evaluated Nuclear Data Library,
Version-1, TAEA-NDS-18 (1979), Vienna.