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KMID : 0371819980300020173
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Nuclear Engineering and Technology
1998 Volume.30 No. 2 p.173 ~ p.179
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Analysis of Corrosion Behavior of KOFA Zircaloy-4 Cladding
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Lee Chan-Bock
Kim Ki-Hang
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Abstract
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The corrosion behavior of KOFA cladding which is a standard Zircaloy-4 manufactured by .Westinghouse Specialty Metal Plant according to the Siemens/KWU´s HCW (Highly Cold Worked) standard Zircaloy4 specification was analyzed using the oxide measurement data of KOFA fuel irradiated in Kori-2 nuclear power plant. Analysis of the measured KOFA cladding oxidation showed that oxidation of KOFA cladding was lower than the design prediction based upon Siemens/KWU´s HCW standard Zircaloy-4 cladding. Although the measured fuel rods have relatively low burnup and oxidation and the amount of the measured data are small, analysis of manufacturing and in-reactor operation conditions of KOFA cladding indicates that the differences in the manufacturing processes and chemical composition of the Siemens/KWU´s HCW (Highly Cold Worked) standard Zircaloy-4 and KOFA cladding may have somewhat contributed to lower corrosion of KOFA cladding than the expected.
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KEYWORD
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