JAERI 1287 JNDC Nuclear Data Library of Fission Products Fir

20 JNDC Nuclear Data library of Fission Products JAER11287
The capture energy Qc can be given as
Qe = (j/-1)Q«, (2.5.12)
where Qnc is the capture energy per captured neutron and it was estimated to be 6.53 ± 0.2
MeV for a 23s U-fueled FBR-II type of fast reactor by Unik and Gindler 52) and to be 6.1 ± 0.3
MeV for thermal reactor by James sl) . The value for the fast reactor is also used for the 14
MeV neutron fissions in the present evaluation. The summary of Qe/f and QT are given in
Table 2.5.3.
2.6 Neutron Capture Cross Section
The neutron capture is the only reaction involved for the transmutation of fission
product nuclides. The neutron capture cross section data have been prepared for 80 fission
product nuclides as listed in Table 2.6.1. The neutron capture cross section data for 54 fission
product nuclides have been evaluated by other working group of JNDC for JENDL-1 and
.254,ss) ancj the (jata are compiieci j n the present library. The data for the remaining 26 nuclides
have been taken from ENDF/B-IV.
These neutron capture cross sections have been converted to twenty-seven group cross
sections. The group structure is shown in Table 2.6.2. Groups 1 to 25, in Table 2.6.2, are for
fast reactor calculations. Groups 26 and 27 are for thermal reactor calculations. The resonance
capture integral is given in Group 26. The lower-energy limit for the resonance integral is 0.5
eV. The thermal neutron capture cross section, for 2200 m/s-neutrons, is given in Group 27.
For fast reactor calculations, the 25-group neutron capture cross sections were calculated
by the computer code SUPERTOG S6) using the nuclear data evaluated by Japanese Nuclear
Data Committee (JNDC) for 54 nuclides, which cover more than 80% of the total neutron
No.
1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
16
17
18
19
20
Table 2.6.1 Fission product nuclides with neutron capture cross section data
in the present library
Nuclide
79 Se
84 Kr
85 Kr
85 Rb
87 Kr
87 Rb
89y
90
Sr
91
Zr
92
Zr
93
Zr
94
Zr
95
Mo
96
Zr
97
Mo
98
Mo
99
Tc
100
Mo
100 Ru
101 Ru
No.
21
22
23
24
25
26
27
28
29
30
31
32
33
34
35
36
37
38
39
40
Nuclide
102 Ru
103 Rh
104 Ru
104 Rh
10s Rh
iospd
106 Ru
107pd
lOSpj
109 Ag
uopd
113 Cd
lls In
121 Sb
123 Sb
127 I
.28Te
129j
130 Te
13I Xe
No.
41
42
43
44
45
46
47
48
49
50
51
52
53
54
55
56
57
58
59
60
Nuclide
133 Xe
133 Cs
134
Cs
135
Xe
13s
Cs
137
Cs
138
Ba
139
La
140
Ba
140
Ce
141
Ce
141pr
142 Ce
143pr
143 Nd
144 Ce
144 Nd
145 Nd
146 Nd
147 Pm
No.
61
62
63
64
65
66
67
68
69
70
71
72
73
74
75
76
77
78
79
80
Nuclide
147 Sm
148 Nd
148
Pm
148
Sm
149
Pm
149
Sm
150
Nd
150
Sm
15I
Sm
lsl
Eu
152
Sm
153
Eu
154
Sm
154
Eu
155
Eu
155
Gd
155 Eu
158 Gd
159Tb
148mpm