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Sensitivity analyses of initial compositions and cross sections were conducted to quantitatively clarify the source elements and the nuclear reactions dominating the generation of activation products. In these analyses, the ORIGEN2.2 code was used with ORLIBJ40, a set of the cross-section libraries based on JENDL-4.0. Analyses were conducted for the activations of cladding tubes, end plugs, and spacers of fuel assemblies and channel boxes in BWR that are composed of zirconium alloy, stainless steel, and nickel-chromium-based alloy. From about 50 representative radioactive nuclides, several nuclides were selected as the targets of sensitivity analyses for the aspect of their large concentrations in the target materials.
The results of sensitivity coefficients clarified the source elements and the nuclear reactions dominating the generation of activation products even for the nuclides generated through complicated pathways. These results could be utilized to select the objectives of the impurity elements for measurements and of nuclear data for the improvement of accuracy. These results will contribute to improvements in the accuracy of numerical evaluations of activation product concentrations.
Ludwig SB, Croff AG (1998) Revision to ORIGEN2: version 2.2. Transmittal memo of CCC-0371/17. Oak Ridge National Laboratory, Oak Ridge
Okumura K, Sugino K, Kojima K, Jin T, Okamoto T, Katakura J (2012) A set of ORIGEN2 cross section libraries based on JENDL-4.0: ORLIBJ40. JAEA Data/Code 2012-032. Japan Atomic Energy Agency [in Japanese], Ibaraki
Shibata K, Iwamoto O, Nakagawa T, Iwamoto N, Ichihara A, Kunieda S, Chiba S, Furukawa K, Otuka N, Ohsawa T, Murata T, Matsunobu H, Zukaran A, Kameda S, Katakura J (2011) JENDL-4.0: a new library for nuclear science and engineering. J Nucl Sci Technol 48(1):1–30 CrossRef
Namekawa M, Fukahori T (2012) Tables of nuclear data (JENDL/TND-2012). JAEA Data/Code 2012-014. Japan Atomic Energy Agency, Ibaraki
Evans JC, Lepel EL, Sanders RW, Wilkerson CL, Silker W, Thomas CW, Abel KH, Robertson DR (1984) Long-lived activation products in reactor materials. NUREG/CR-3474. U.S. Nuclear Regulatory Commission, Washington
Atomic Energy Society of Japan (2010) AESJ-SC-F015: basic procedure to determine the activity concentration of sub-surface disposal waste [in Japanese]
- Sensitivity Analyses of Initial Compositions and Cross Sections for Activation Products of In-Core Structure Materials
- Springer Japan
- Chapter 20
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