8 Sensitivity and Uncertainty of Criticality
229
(a) EE1 core
(b) E3 core
-4.5E-02
-3.5E-02
-2.5E-02
-1.5E-02
-5.0E-03
5.0E-03
1.0E-04
1.0E-02
1.0E+00
1.0E+02
1.0E+04
1.0E+06
Sensitivity coefficient per lethargy [-]
Neutron energy [eV]
Al-27
B-10
B-11
C-12
H-1
O-16
U-234
U-235
U-236
U-238
H-1
U-235
B-10
Al-27
-4.5E-02
-3.5E-02
-2.5E-02
-1.5E-02
-5.0E-03
5.0E-03
1.0E-04
1.0E-02
1.0E+00
1.0E+02
1.0E+04
1.0E+06
Sensitivity coefficient per lethargy [-]
Neutron energy [eV]
Al-27
B-10
B-11
C-12
H-1
O-16
U-234
U-235
U-236
U-238
Al-27
H-1
U-235
B-10
Fig. 8.7 Sensitivity coefficients for capture reactions in C1 rod worth (Ref. [1])
Table 8.6 Reaction-wise contribution [pcm] to excess reactivity induced by covariance data of
JENDL-4.0 in EE1 core (Ref. [1])
Isotopes
Reactions
Capture
Elastic
Inelastic
Fission
(n, 2n)
Total
10 B
0.0
0.0
–
–
–
0.0
11 B
0.0
0.0
–
–
–
0.0
16 O
0.0
0.0
0.0
–
0.0
0.0
235 U
111.7
5.3
12.9
44.7
0.7
121.1
238 U
2.8
0.2
0.9
0.1
0.1
2.9
Total
135.8