202
C. H. Pyeon
Fig. 7.14 (continued)
(c) ENDF/B-VII.0 versus JENDL-4.0
(d) JEFF-3.1 versus JENDL-4.0
-8.0
-6.0
-4.0
-2.0
0.0
2.0
4.0
Pb-204
Pb-206
Pb-207
Pb-208
Reactivity (E70 - J40) [pcm]
capture
elastic
inelastic
-8.0
-6.0
-4.0
-2.0
0.0
2.0
4.0
Pb-204
Pb-206
Pb-207
Pb-208
Reactivity (F31 - J40) [pcm]
capture
elastic
inelastic
Nonetheless, from all the results of sensitivity coefficients, absolute values of
209 Bi
were markedly very small in vertical axes shown in Figs. 7.15, 7.16 and 7.17, as
compared with the values of
27 Al and
235 U, demonstrating that the impact of
209 Bi
cross sections was considered minor in the sensitivity coefficient analyses of k eff in
the Bi sample reactivity worth experiments at KUCA.
7.4 Uncertainty Quantification
7.4.1 Theoretical Background
7.4.1.1 Uncertainty
As for the cross-section uncertainty analyses of nuclear data [23], the uncertainty of
reactor physics parameters ν can be expressed as follows: