Table 20.6 Concentration of activation products and fission products
Nuclide
Concentration of
activation products
(g/t)
Concentration of fission
products (g/t)
Comparison
(%)
Target
nuclide
①Zry-2
②Zry-4
③
③ /(①+③)
(a) Zircaloy-2 and Zircaloy-4
Zr-93
2.0E + 02 2.0E + 02 1.2E-03
0
○
Ni-59
3.7E + 00 4.7E-01
–
–
○
Ni-63
6.6E-01
8.9E-02
–
–
○
Co-60
5.1E-01
5.1E-01
–
–
○
C-14
4.0E-01
4.0E-01
–
–
○
Nb-94
3.0E-01
3.0E-01
3.2E-09
0
○
Sb-125 2.5E-01
2.5E-01
1.5E-06
0
○
Ca-41
3.0E-02
3.0E-02
–
–
○
K-40
2.2E-02
2.2E-02
–
–
○
Fe-55
2.1E-02
3.2E-02
–
–
○
Tc-99
9.1E-03
9.1E-03
1.7E-03
16
○
Mo-93
8.9E-03
8.9E-03
3.5E-14
0
○
Be-10
4.0E-05
4.0E-05
2.2E-08
0
○
Sr-90
2.3E-05
2.3E-05
6.0E-04
96
–
Mn-54
3.9E-06
6.1E-06
–
–
○
Ag108m
3.3E-07
3.3E-07
5.6E-12
0
○
Rb-87
1.1E-07
1.1E-07
3.7E-04
100
–
H-3
3.0E-08
3.0E-08
5.8E-08
66
○
I-129
6.4E-09
6.4E-09
3.9E-04
100
–
Zn-65
2.8E-09
2.8E-09
–
–
○
(b) SUS304 stainless steel
Nuclide Concentration of activation products (g/t)
Concentration of fission products (g/t)
Comparison
(%)
Target
nuclide
①Bottom ②Top
③
③ /(①+③)
Ni-59
4.8E + 01 2.6E + 01 –
–
○
Ni-63
7.7E + 00 4.1E + 00 –
–
○
Fe-55
7.0E-01
3.9E-01
–
–
○
Co-60
5.3E-03
5.0E-03
–
–
○
Mn-54
9.9E-05
9.9E-05
–
–
○
Be-10
5.7E-06
5.7E-06
2.0E-10
0
○
C-14
3.2E-06
2.3E-06
–
–
○
Cl-36
1.6E-06
4.4E-07
–
–
○
(continued)
240
K. Yamamoto et al.
Nuclide
Concentration of
activation products
(g/t)
Concentration of fission
products (g/t)
Comparison
(%)
Target
nuclide
①Zry-2
②Zry-4
③
③ /(①+③)
(a) Zircaloy-2 and Zircaloy-4
Zr-93
2.0E + 02 2.0E + 02 1.2E-03
0
○
Ni-59
3.7E + 00 4.7E-01
–
–
○
Ni-63
6.6E-01
8.9E-02
–
–
○
Co-60
5.1E-01
5.1E-01
–
–
○
C-14
4.0E-01
4.0E-01
–
–
○
Nb-94
3.0E-01
3.0E-01
3.2E-09
0
○
Sb-125 2.5E-01
2.5E-01
1.5E-06
0
○
Ca-41
3.0E-02
3.0E-02
–
–
○
K-40
2.2E-02
2.2E-02
–
–
○
Fe-55
2.1E-02
3.2E-02
–
–
○
Tc-99
9.1E-03
9.1E-03
1.7E-03
16
○
Mo-93
8.9E-03
8.9E-03
3.5E-14
0
○
Be-10
4.0E-05
4.0E-05
2.2E-08
0
○
Sr-90
2.3E-05
2.3E-05
6.0E-04
96
–
Mn-54
3.9E-06
6.1E-06
–
–
○
Ag108m
3.3E-07
3.3E-07
5.6E-12
0
○
Rb-87
1.1E-07
1.1E-07
3.7E-04
100
–
H-3
3.0E-08
3.0E-08
5.8E-08
66
○
I-129
6.4E-09
6.4E-09
3.9E-04
100
–
Zn-65
2.8E-09
2.8E-09
–
–
○
(b) SUS304 stainless steel
Nuclide Concentration of activation products (g/t)
Concentration of fission products (g/t)
Comparison
(%)
Target
nuclide
①Bottom ②Top
③
③ /(①+③)
Ni-59
4.8E + 01 2.6E + 01 –
–
○
Ni-63
7.7E + 00 4.1E + 00 –
–
○
Fe-55
7.0E-01
3.9E-01
–
–
○
Co-60
5.3E-03
5.0E-03
–
–
○
Mn-54
9.9E-05
9.9E-05
–
–
○
Be-10
5.7E-06
5.7E-06
2.0E-10
0
○
C-14
3.2E-06
2.3E-06
–
–
○
Cl-36
1.6E-06
4.4E-07
–
–
○
(continued)
240
K. Yamamoto et al.
