金属学报  2010, Vol. 46 Issue (10): 1267-1274    DOI: 10.3724/SP.J.1037.2010.00199

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Ü690合金在高温水中的应力腐蚀裂纹扩展行为

但体纯1, 吕战鹏 2, 王俭秋1,韩恩厚1,庄子哲雄2,柯伟1

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

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

DAN Tichun 1, LÜ Zhanpeng 2, WANG Jianqiu 1, HAN Enhou 1, SHOJI Testuo 2, KE Wei 1

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

但体纯 吕战鹏 王俭秋 韩恩厚 庄子哲雄 柯伟. 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.
, , , , , . CRACK GROWTH BEHAVIOR FOR STRESS CORROSION CRACKING OF 690 ALLOY IN HIGH TEMPERATURE WATER[J]. Acta Metall Sin, 2010, 46(10): 1267-1274.

摘要 参考文献 相关文章 Metrics 全文: PDF(3989 KB)   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. 关键词 ： 应力腐蚀,  裂纹扩展,  交流电位降,  高温水     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. Key words： stress corrosion cracking (SCC)    crack growth    alternative current potential drop(ACPD)     high–temperature water 收稿日期: 2010-04-26      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 作者简介: 但体纯, 男, 1981年生, 博士生 服务 把本文推荐给朋友 加入引用管理器 E-mail Alert RSS 作者相关文章 但体纯 韩恩厚 吕战鹏 柯伟 王俭秋 T. Shoji 44.8K 链接本文: https://www.ams.org.cn/CN/10.3724/SP.J.1037.2010.00199      或      https://www.ams.org.cn/CN/Y2010/V46/I10/1267 [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. 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