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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2012.1
- 수록면
- 96 - 102 (7page)
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초록· 키워드
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Outer diameter stress corrosion cracking (ODSCC) has occurred for Alloy 600 (Ni 75 wt%, Cr 15 wt%, Fe 10 wt%) as a heat exchanger tube of the steam generator (SG) in nuclear power plants (NPP) during long term operation. Among many causes for SCC, lead (Pb) is known to be one of the most deleterious species in the secondary system. In the present work, the oxide formed on Alloy 600 was characterized as a function of the PbO content in 0.1 M NaOH at 315 ℃ by using an electrochemical impedance spectroscopy (EIS), a transmission electron microscopy (TEM), equipped with an energy dispersive x-ray spectroscopy (EDS). The oxide property was analyzed in view of SCC susceptibility.
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참고문헌 (10)
참고문헌 신청
/ / HSC Chemistry Database, 6.0
/ 2003 / NUREG report
/ 2008 / MULTEQ calculation performed at ANL
A. Baum / 2005 / / Proc. of 12th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors : 1155 ~
A. J. Bard / 1980 / Electrochemical Methods, Fundamentals and Applications / John Wiley & Sons : 323 ~
/ 2003 / NUREG report
/ 2008 / MULTEQ calculation performed at ANL
A. Baum / 2005 / / Proc. of 12th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors : 1155 ~
A. J. Bard / 1980 / Electrochemical Methods, Fundamentals and Applications / John Wiley & Sons : 323 ~
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