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14 декабря, 2021
The representative radioactive nuclides in this study (Table 20.5) include not only the important nuclides for various evaluations of radioactive wastes but also the nuclides whose concentrations have been measured in the past, which will be useful for the validation of numerical evaluations.
Target nuclides of sensitivity analyses were selected on the basis of two criteria. The first was that the concentrations of activation products be larger than or comparable to the concentration of fission products generated from impurity uranium in the materials. The contents of impurity uranium in Zircaloy-2 and SUS304 stainless steel were 0.00035 wt% and 0.0001 wt% [5], respectively. This value in INCONEL alloy is unknown. The second criterion was that the concentrations of activation products be comparatively large. In these analyses, activation products with concentrations more than 1 x 10~9 g/t were chosen.
The concentrations of activation products larger than 1 x 10~9 g/t and fission products generated from impurity uranium are shown in Table 20.6. The fission products were calculated under the condition that the initial composition contains only the uranium impurity. Table 20.6 also shows the selected target nuclides that satisfy the foregoing criterion: 17 nuclides in Zircaloy-2 and Zircaloy-4, 8 nuclides in SUS304 stainless steel, and 16 nuclides in INCONEL alloy were selected as the target nuclides of sensitivity analyses.
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Concentration of activation products |
Concentration of fission |
Comparison |
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(g/t) |
products (g/t) |
(%) |
Target |
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Nuclide |
©Zry-2 |
©Zry-4 |
© |
©/(©+©) |
nuclide |
(a) Zircaloy-2 and Zircaloy-4 |
Zr-93 |
2.0E + 02 |
2.0E + 02 |
1.2E-03 |
0 |
о |
Ni-59 |
3.7E + 00 |
4.7E-01 |
— |
— |
О |
Ni-63 |
6.6E-01 |
8.9E-02 |
— |
— |
О |
Co-60 |
5.1E-01 |
5.1E-01 |
— |
— |
О |
C-14 |
4.0E-01 |
4.0E-01 |
— |
— |
О |
Nb-94 |
3.0E-01 |
3.0E-01 |
3.2E-09 |
0 |
О |
Sb-125 |
2.5E-01 |
2.5E-01 |
1.5E-06 |
0 |
О |
Ca-41 |
3.0E-02 |
3.0E-02 |
— |
— |
О |
K-40 |
2.2E-02 |
2.2E-02 |
— |
— |
О |
Fe-55 |
2.1E-02 |
3.2E-02 |
— |
— |
О |
Tc-99 |
9.1E-03 |
9.1E-03 |
1.7E-03 |
16 |
О |
Mo-93 |
8.9E-03 |
8.9E-03 |
3.5E-14 |
0 |
О |
Be-10 |
4.0E-05 |
4.0E-05 |
2.2E-08 |
0 |
О |
Sr-90 |
2.3E-05 |
2.3E-05 |
6.0E-04 |
96 |
— |
Mn-54 |
3.9E-06 |
6.1E-06 |
— |
— |
О |
Ag- 108m |
3.3E-07 |
3.3E-07 |
5.6E-12 |
0 |
О |
Rb-87 |
1.1E-07 |
1.1E-07 |
3.7E-04 |
100 |
— |
H-3 |
3.0E-08 |
3.0E-08 |
5.8E-08 |
66 |
О |
I-129 |
6.4E-09 |
6.4E-09 |
3.9E-04 |
100 |
— |
Zn-65 |
2.8E-09 |
2.8E-09 |
— |
— |
О |
(b) SUS304 stainless steel |
Nuclide |
Concentration of acti- |
Concentration of fission prod- |
Comparison |
Target |
|
vation products (g/t) |
ucts (g/t) |
(%) |
nuclide |
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©Bottom |
©Top |
© |
©/(©+©) |
||
Ni-59 |
4.8E + 01 |
2.6E + 01 |
— |
— |
О |
Ni-63 |
7.7E + 00 |
4.1E + 00 |
— |
— |
О |
Fe-55 |
7.0E-01 |
3.9E-01 |
— |
— |
О |
Co-60 |
5.3E-03 |
5.0E-03 |
— |
— |
О |
Mn-54 |
9.9E-05 |
9.9E-05 |
— |
— |
О |
Be-10 |
5.7E-06 |
5.7E-06 |
2.0E-10 |
0 |
О |
C-14 |
3.2E-06 |
2.3E-06 |
— |
— |
О |
Cl-36 |
1.6E-06 |
4.4E-07 |
— |
— |
О |
(continued) |
Table 20.6 (continued)
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(c) INCONEL alloy 718
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