论文

Ü690合金在高温水中的应力腐蚀裂纹扩展行为

  • 但体纯 ,
  • 韩恩厚 ,
  • 吕战鹏 ,
  • 柯伟 ,
  • 王俭秋 ,
  • T. Shoji
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  • 1. 中国科学院金属研究所腐蚀与防护国家重点实验室, 沈阳 110016
    2. 日本东北大学断裂与可靠性研究中心, 仙台 980--8579
但体纯, 男, 1981年生, 博士生

收稿日期: 2010-04-26

  修回日期: 2010-07-07

  网络出版日期: 2010-10-11

基金资助

国家重点基础研究发展计划项目G2006CB60500和日本PEACE--E项目资助

CRACK GROWTH BEHAVIOR FOR STRESS CORROSION CRACKING OF 690 ALLOY IN HIGH TEMPERATURE WATER

  • DAN Ben-Quan ,
  • HAN En-Hou ,
  • LV Zhan-Peng ,
  • KE Wei ,
  • YU Jian-Qiu
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  • 1. Environmental Corrosion Center, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016
    2. Fracture and Reliability Research Institute, Tohoku University, Sendai 980–8579, Japan

Received date: 2010-04-26

  Revised date: 2010-07-07

  Online published: 2010-10-11

Supported by

Supported by National Basic Research Program of China (No.G2006CB60500) and "Prediction of
Environmental Assisted Cracking Evaluation–E"(PEACE–E) Program of Japan

摘要

用交流电位降(ACPD)技术实现了模拟压水堆一回路340℃高温水环境中690合金应力腐蚀裂纹扩展的实时监测. 断口观察表明, 2种一维冷加工690合金均出现沿晶应力腐蚀裂纹扩展, 裂纹沿平行轧制方向的扩展速率略高于垂直轧制方向的速率; 当溶解H浓度(CdH)由30 μL/g减小到10 μL/g时, 经1075℃退火和700℃固溶处理15 h并一维冷轧25%的T-L取向690合金的平均裂纹扩展速率由4.8×10-11 m/s增加至11.2×10-11 m/s; 应力腐蚀裂纹扩展主要为内氧化机制.

本文引用格式

但体纯 , 韩恩厚 , 吕战鹏 , 柯伟 , 王俭秋 , T. Shoji . Ü690合金在高温水中的应力腐蚀裂纹扩展行为[J]. 金属学报, 2010 , 46(10) : 1267 -1274 . DOI: 10.3724/SP.J.1037.2010.00199

Abstract

Stress corrosion crack growth rates of alloy 690 thermally treated (TT) after one–directionally (1D) cold–rolling along the longitudinal (L) direction and three–directionally (3D) cold–rolling were successfully measured by ACPD technique in deoxygenated water with different dissolved hydrogen contents (CdH) at 340 ℃. The fracture mode is mainly intergranular mode in both two kinds of alloy 690TT. The crack growth rates in the T–L orientation are higher than those in the L–T orientation in 340 ℃deoxygenated environments. For 1D 25% alloy 690TT with T–L orientation, the measured average crack growth rate is 4.8×10−11 m/s in 340℃ water with CdH 30 μL/g, and the measured average crack growth rate is 1.1×10−10 m/s in 340 ℃ water with CdH 10 μL/g. The mechanism of crack growth is internal oxidation mechanism.

参考文献

[1] Speidel M O, Magdowski R. 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors,edited by Gold R E, Simonen E P.(1993): 361-371.
[2] Moshier W C, Brown C M. Corrosion, 2000, Vol. 56(No. 3): 307-320.
[3] Yamazaki S, Lu Z P, Ito Y, Takeda Y, Shoji T. Corros Sci, 2008, Vol. 50(2008): 835-846.
[4] Rebak R B, Szklarska-Smialowska Z. Corros Sci, 1996, Vol. 38, No. 6(1996): 971-988.
[5] Page R A, Mcminn A. Metall Trans A, 1986, Vol. 17A, No. 5(1986): 877-887.
[6] Andresen P L, Hickling J, Ahluwalia A, Wilson J. Corrosion, 2008, Vol. 64(2008): 707-720.
[7] Vaillant F, Mitheux J D, Bouvier O, Vancon D, Zacharie G, Brechet Y, Louchet F. 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors,edited by Ford F P, Bruemmer S M, Was G S.(1999): 251-260
[8] Sui G, Titchmarsh J M, Heys G B, Congleton J. Corros Sci, 1997, Vol. 39(No. 3): 565-587.
[9] Scenini F, Newman R C, Cottis R A, Jacko R J. 12th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors,edited by Allen T R, King P J, Nelson L.(2005): 891-901
[10] Young B A, Gao X, Srivatsan T S, King P J. Materials and Design. 2007. Vol. 28: 373-379.
[11] Lu Z, Shoji T, Takeda Y, Kai A, Ito Y. Corrosion. 2007. Vol. 63(No. 11): 1020-1032.
[12] Lu Z P, Shoji T, Takeda Y, Ito Y, Yamazaki S. Corros Sci, 2008, Vol. 50: 698-712.
[13] Lu Z P, Shoji T, Takeda Y, Ito Y, Kai A, Tsuchiya N. Corros Sci. 2008. Vol. 50: 625-638.
[14] Lu Z P, Shoji T, Takeda Y, Ito Y, Kai A, Yamazaki S. Corros Sci, 2008, Vol. 50: 561-575.
[15] Dan T C. PhD Thesis,Institute of Metal Research, Chinese Academy of Sciences, 2010. (但体纯. 中国科学院金属研究所博士论文,2010)
[16] Shen Y, Shewmon P G. Metall Trans A, 1991, Vol. 22A, No. 8(1991): 1857-1864.
[17] Arioka K, Yamada T, Terachi T, Miyamoto T. Corrosion, 2008, 64(9): 691-706.
[18] Lu Z P, Shoji T, Dan T C, Qiu Y B, Yonezawa T. To be published on Corros Sci, 2010.
[19] Moshier W C, Brown C M. Corrosion. 2000. 56(3): 307-320.
[20] Shoji T, Lu Z P, Das N K, Murakami H, Takeda Y, Ismail T. Proceedings of PVP 2009: 2009 ASME Pressure Vessels and Piping Division Conference,edited by ASME.(2009): 1-20
[21] Marchetti L, Perrin S, Raquet O, Pijolat M. Materials Science Forum. 2008. Vols. 595-598: 529-537.
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