Nuclear Engineering and Technology
- 제30권2호
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- Pages.173-179
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- 1998
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- 1738-5733(pISSN)
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- 2234-358X(eISSN)
Analysis of Corrosion Behavior of KOFA Zircaloy-4 Cladding
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Lee, Chan-Bock
(Korea Atomic Energy Research Institute) ;
- Kim, Ki-Hang (Korea Nuclear Fuel Company)
- 발행 : 1998.04.01
초록
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 Zircaloy-4 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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