Sensitivity Analysis Using the Initial Composition Based on Measured Data

The sensitivity coefficients shown in Sect. 20.3.3 are valid within the assumed analysis conditions in Sect. 20.3.1. However, the impurity elements that are not specified in the standard specification can be possibly present in the material. To know the effect of the difference in the initial composition on sensitivity coeffi­cients, additional analyses were conducted using the initial composition based on measured data. The evaluation of activation products in SUS304 stainless steel is described here.

Table 20.10 Concentration of activation products in SUS304 stainless steel

Подпись: Co-60 1.7E + 00 Fe-55 7.4E-01 C-14 1.7E-01 Cl-36 5.4E-02 Nb-94 3.4E-02 Tc-99 1.2E-02 Mo-93 1.1E-02 K-40 1.8E-04 Mn-54 1.0E-04 Zr-93 6.6E-05 Подпись: NuclideПодпись:Подпись: Ni-59Подпись: 4.8E + 01Подпись: Ni-63Подпись: 7.8E + 00Except for the initial composition, the analysis conditions described in Sect. 20.3.1 were assumed. The composition data reported by the Atomic Energy Society of Japan [6] were applied in this analysis. In this reference, the concentra­tion distributions of some elements with their mean values and standard deviations have been determined based on several measured data. The initial composition based on measured data is shown in Table 20.9 together with that based on the standard specification.

The concentration of activation products using the initial composition based on measured data is shown in Table 20.10. As a matter of course, the concentrations were changed from those in Table 20.6b because the different initial compositions were assumed. It was found that Nb-94, Tc-99, Mo-93, K-40, and Zr-93 appeared in Table 20.10 because of the presence of niobium, molybdenum, and potassium in the initial composition. For the comparison with the sensitivity coefficients shown in Sect. 20.3.3, sensitivity analyses of cross sections were conducted for the several nuclides Ni-59, Ni-63, Fe-55, Co-60, Mn-54, C-14, and Cl-36, which were listed in both Tables 20.6b and 20.10.

The sensitivity coefficients of cross sections using the initial composition based on measured data are shown in Table 20.11. It was found that the results of Co-60, C-14, and Cl-36 are much different from those in Table 20.8b, which indicates that the dominant generation pathways of these nuclides were changed. Figure 20.3 shows the comparison of dominant generation pathways of Co-60, C-14, and Cl-36 between different analysis conditions. The source nuclides of Co-60, C-14, and Cl-36 were Co-59, N-14, and Cl-35, respectively, under the conditions based on measurement data, whereas those were Ni-60, C-13, and S-34, respectively, under the conditions based on the standard specification.

As shown in the foregoing example, the dominant generation pathway can be changed corresponding to the initial composition. The reliable measured data of initial impurity elements should be used if they are available. For any condition, sensitivity analyses on the basis of the methodology stated in this study can systematically identify the dominant generation pathways of activation products.

Target nuclide

First largest

Second largest

Ni-59

Ni-58

(n, Y)

1.00

Ni-63

Ni-62

(n, Y)

1.00

Fe-55

Fe-54

(n, Y)

0.99

Ni-58

(n, a)

0.01

Co-60

Co-59

(n, Y)

0.46

Co-59

(n, Y)m

0.46

Mn-54

Fe-54

(n, p)

1.00

C-14

N-14

(n, p)

1.00

Cl-36

Cl-35

(n, Y)

1.00

Sensitivity coefficient of cross section

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