204
C. H. Pyeon
Fig. 7.16 Sensitivity
coefficients of elastic
scattering reactions of 209 Bi
and 27 Al in JENDL-4.0 (Ref.
[3])
(a)
209
Bi
(b)
27
Al
10
-5 10
-4 10
-3 10
-2 10
-1 10
0 10
1 10
2 10
3 10
4 10
5 10
6 10
7
0
0.0002
0.0004
0.0006
0.0008
0.0010
Neutron energy [eV]
Sensitivity coefficient per lethargy
209 Bi
10
-5 10
-4 10
-3 10
-2 10
-1 10
0 10
1 10
2 10
3 10
4 10
5 10
6 10
7
0
0.05
0.10
Neutron energy [eV]
Sensitivity coefficient per lethargy
27 Al
υ i, j =
g
g
s
i
g c
i, j
g, g s
j
g
1 ≤ g, g
≤ G
.
(7.23)
7.4.1.2 Cross-Section Adjustment Method
In the cross-section adjustment method [24], probability P(T) with a certain crosssection set T is obtained as follows, assuming that a set of nuclear cross sections
provides a true value in normal distribution around a true value T 0 of the nuclear
cross-section set with dispersion M:
P(T) = P(T 0 ) ∝ exp
−(T − T 0 )
t M
−1
(T − T 0 )/2
.
(7.24)
Substituting the values of T 0 , T and M in Eq. (7.24) for those of experiments R e ,
the true value of experiments R e0 and covariance V e of experiment errors, Eq. (7.18)