Chin J Mater Res  1996, Vol. 10 Issue (2): 140-144    DOI:

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THE CREVICE CORROSION OF ZIRCALOY-4,A COAT MATERIAL OF NUCLEAR FUEL

XU Chunchun;CEN Yanqing; DANG Yanchun(Beijing University of Chemical Technology)Correspondent: (Beijing University of Chemical Technology; Beijing 100029)

XU Chunchun;CEN Yanqing; DANG Yanchun(Beijing University of Chemical Technology)Correspondent: (Beijing University of Chemical Technology; Beijing 100029). THE CREVICE CORROSION OF ZIRCALOY-4,A COAT MATERIAL OF NUCLEAR FUEL. Chin J Mater Res, 1996, 10(2): 140-144.

Abstract References Related Articles Recommended Metrics Download:  PDF(478KB)  Export:  BibTeX | EndNote (RIS)       Abstract  A simulated occluded corrosion cell was used to study the susceptibilities to crevice corrosion o f irradiated and unirradiated zircaloy-4 in NaCl solution.It was found that in the occluded cell pH value drops and the concentration of Cl-increases as anod Key words:  irradiation zircaloy-4;crevice corrosion;occluded cell      Received:  25 April 1996      Service E-mail this article Add to citation manager E-mail Alert RSS （） Articles by authors URL:  https://www.cjmr.org/EN/     OR     https://www.cjmr.org/EN/Y1996/V10/I2/140 1AdrianRobertsJT．StructuralMarerialsinNuclcarPowerSystems,1981:462陈鹤鸣,马春来,白新德．核反应堆材料腐蚀及其防护．1984:1883Katsura．Corrosion,1992,48:3844H．Stehle等压水堆元件包壳的外表面腐蚀,原子能译丛,1997,4:5ChengB,AdamsonRB．ZirconiumintheNuclearIndustry,SeventhInternationalSymposium,ASRMSTP939,1987:3876BrownBFCorrosion,1970,26:2497PourbaixM．In:ScullyJCed．Thetheoryofstresscorrosioncrackinginalloys,1971:178左景伊,金志强．化工学报,1982,4:2919HliilnerE．ZirconiuminNuclearIndustry,ASTMSTP633,1977:211V No related articles found! No Suggested Reading articles found! Viewed Full text Abstract Cited   Shared      Discussed