화학공학소재연구정보센터
학회 한국재료학회
학술대회 2006년 봄 (05/19 ~ 05/20, 경상대학교 )
권호 12권 1호
발표분야 에너지환경재료
제목 Corrosion Characteristics of T91 at a 450oC Lead Loop
초록 Liquid lead-alloy is one of the coolant materials used for the nuclear reactors which will be developed in the future. Lead is one of such lead-alloys. Since the melting point of lead is 327oC, the temperature of the reactor coolant should be grater than 400oC. It is known that the steel structure material of the reactor can be damaged by the corrosion of high temperature lead. KAERI(Korea Atomic Energy Research Institute) built lead-alloy corrosion test loops called KPAL(KAERI Pb-Alloy Loop). KPAL-I and KPAL-II are Pb-Bi and Pb loop respectively. In this study, KPAL-II was used to investigate the Pb corrosion characteristics of T91 at 450oC. The exposure time was 300 hrs. The oxygen content in Pb was controlled by injecting the mixed gas of Ar5%H2 and H2O vapor. Then oxide layer can be formed on the T91 surface to prevent Pb corrosion. The effect of oxide layer on corrosion was also studied.
저자 송태영, 조충호, 조춘호
소속 한국원자력(연)
키워드 Lead-alloy; Corrosion; Loop
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