Microstructural aspects of Zircaloy nodular corrosion in steam

被引:11
|
作者
Taylor, DF [1 ]
机构
[1] GE, Corp Res & Dev, Schenectady, NY 12301 USA
关键词
D O I
10.1016/S0022-3115(99)00159-2
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Zircaloy-2 becomes susceptible to nodular corrosion in high-temperature, high-pressure steam when the total solute concentration of the beta-stabilizing alloying elements Fe, Ni and Cr in the alpha-zirconium matrix falls below a critical value C-c that is characteristic of the test conditions. C-c for typical commercial Zircaloy-2 in a 24 h/510 degrees C/10.4 MPa steam-test is the precipitate-free alpha-matrix concentration in equilibrium with solute-saturated beta phase at about 840 degrees C, the corresponding critical temperature T-c. Thus, immunity to nodular corrosion is a metastable condition for alpha-Zircaloy that requires fast cooling from above T-c to achieve adequate solute concentration throughout the matrix. Annealing Zircaloy at any temperature below T-c for a sufficiently long time makes it susceptible to nodular corrosion, in the (alpha + chi) phase field, where chi collectively designates the Fe-, Cr- and Ni-containing precipitate phases, lowering the solute concentration to less than C-c by Ostwald ripening can require many hundreds of hours. Above about 825 degrees C, the temperature of the (alpha + chi)/(alpha + beta + chi) transus, solute-saturated beta phase surrounds each precipitate and a strong 'inverse' activity gradient promotes equilibration with the much lower solute concentration in the alpha matrix. Sensitization to nodular corrosion occurs most rapidly at about 835 degrees C between the (alpha + chi)/(alpha + beta +chi) transus and T-c. Annealing Zircaloy at temperatures above T-c for a sufficiently long time will raise the solute concentration above C-c, and with rapid cooling, heal any degree of susceptibility. Annealing within the 'protective coarsening window' between T-c and about 850 degrees C, the temperature of the (alpha + beta + chi)/(alpha + beta) transus, achieves rapid precipitate growth in a matrix immune to nodular corrosion. (C) 2000 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:295 / 314
页数:20
相关论文
共 50 条
  • [31] MICROSTRUCTURAL AND FRACTOGRAPHIC ASPECTS OF CORROSION FATIGUE
    DICKSON, JI
    LI, SQ
    BAILON, JP
    MATERIALS CHARACTERIZATION, 1992, 28 (04) : 327 - 347
  • [32] CORROSION OF ZIRCALOY-2 IN HIGH TEMPERATURE FLOWING WATER AND STEAM
    SHIMIZU, Y
    ITO, G
    USUKI, R
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1973, 10 (05) : 327 - 327
  • [33] EFFECTS OF MICROCHEMISTRY AND PRECIPITATE SIZE ON NODULAR CORROSION-RESISTANCE OF ZIRCALOY-2
    KRUGER, RM
    ADAMSON, RB
    BRENNER, SS
    JOURNAL OF NUCLEAR MATERIALS, 1992, 189 (02) : 193 - 200
  • [34] Specific Aspects of Internal Corrosion of Nuclear Clad made of Zircaloy
    Minne, J. B.
    Desgranges, L.
    Optasanu, V.
    Largenton, N.
    Raceanu, L.
    Montesin, T.
    DIFFUSION IN MATERIALS - DIMAT 2011, 2012, 323-325 : 227 - +
  • [35] Effect of β Phase Cooling Rate on Nodular Corrosion Resistance of Zircaloy-4 Alloy
    Chen Chuanming
    Zhou Bangxin
    Yao Meiyi
    Gou Shaoqiu
    Zhang Jinlong
    Li Qiang
    Liang Xue
    RARE METAL MATERIALS AND ENGINEERING, 2016, 45 (10) : 2703 - 2709
  • [36] Relationship between Nodular Corrosion Resistance and Grain Orientation of Zircaloy-4 Alloy
    Chen Chuanming
    Zhou Bangxin
    Xu Long
    Gou Shaoqiu
    Huang Jiao
    Zhang Jinlong
    Yao Meiyi
    RARE METAL MATERIALS AND ENGINEERING, 2016, 45 (12) : 3213 - 3217
  • [37] EFFECT OF BETA-HEAT TREATMENT ON MICROSTRUCTURE AND NODULAR CORROSION OF ZIRCALOY-4
    JEONG, YH
    RHEEM, KS
    CHOI, CS
    KIM, YS
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1993, 30 (02) : 154 - 163
  • [38] Autoclave steam corrosion performance of Nb+ implanted Zircaloy-4
    Xue, XY
    Bai, XD
    Zhou, QS
    Tian, ZY
    RARE METAL MATERIALS AND ENGINEERING, 2006, 35 (01) : 34 - 38
  • [39] IN-PILE CORROSION OF ZIRCALOY-2 IN STEAM-WATER MIXTURES
    CERRAI, E
    GADDA, F
    SCARONI, A
    ENERGIA NUCLEARE, 1968, 15 (11): : 722 - &
  • [40] OXIDATION OF ZIRCALOY BY STEAM
    MOALEM, M
    OLANDER, DR
    JOURNAL OF NUCLEAR MATERIALS, 1991, 182 : 170 - 194