高温浓碱溶液浸泡法测试机械堵头应力腐蚀开裂敏感性的有效性
Effectiveness of Determination of Stress Corrosion Cracking Susceptibility of Pull-Out Plug by High Temperature Concentrated Alkali Solution Immersion Test
摘 要
通过高温浓碱溶液浸泡试验以及截面形貌观察,测试了690镍基合金机械拉拔式堵头(封装堵头试样)的应力腐蚀开裂(SCC)敏感性。结果表明:堵头胀接过渡区出现明显的沿晶应力腐蚀裂纹,其SCC敏感性明显高于堵头其他区域,这是由于胀接过渡区域局部塑性变形不连续而出现较高的局部残余应力,在高温浓碱溶液的共同作用下出现了显著的SCC。多个封装试样的测试结果表明本方法可以有效评价堵头试样的SCC敏感性。
机械堵头
胀管过渡区
应力腐蚀开裂
碱性溶液
690 alloy
mechanical plug
roll transition zone
stress corrosion cracking
caustic solution
Abstract
The stress corrosion cracking (SCC) sensitivity of 690 nickel base alloy mechanical pull-out plug (encapsulated plug sample) was tested by immersion test in high temperature concentrated alkali solution and observation of cross section morphology. The results showed that there were obvious intergranular stress corrosion cracks in the expansion transition zone of the plug, and its SCC sensitivity was significantly higher than that of other areas of the plug. This was because the localized plastic deformation in the expansion transition zone was discontinuous, resulting in higher localized residual stress. Under the joint action of high-temperature concentrated alkali solution, significant SCC appeared. The test results of multiple encapsulated plugs indicated that this method could effectively evaluate the SCC sensitivity of plug samples.
中图分类号 TG174 DOI 10.11973/fsyfh-202307002
所属栏目 试验研究
基金项目 国家自然科学基金项目(51771107)
收稿日期 2023/3/20
修改稿日期
网络出版日期
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引用该论文: LIU Pan,DING Ming,HU Huihua,XU Xinhe,CUI Tongming,Lü Zhanpeng. Effectiveness of Determination of Stress Corrosion Cracking Susceptibility of Pull-Out Plug by High Temperature Concentrated Alkali Solution Immersion Test[J]. Corrosion & Protection, 2023, 44(7): 7
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参考文献
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【3】HUANG J B,WU X Q,HAN E H. Electrochemical properties and growth mechanism of passive films on Alloy 690 in high-temperature alkaline environments[J]. Corrosion Science,2010,52(10):3444-3452.
【4】HOU Q,LIU Z Y,LI C T,et al. The mechanism of stress corrosion cracking of Alloy 690TT in a caustic solution containing lead[J]. Corrosion Science,2017,128:154-163.
【5】HWANG S S,KIM H P,LIM Y S,et al. Transgranular SCC mechanism of thermally treated alloy 600 in alkaline water containing lead[J]. Corrosion Science,2007,49(10):3797-3811.
【6】KIM D J,KIM H P,HWANG S S. Susceptibility of alloy 690 to stress corrosion cracking in caustic aqueous solutions[J]. Nuclear Engineering and Technology,2013,45(1):67-72.
【7】KIM D J,KWON H C,KIM H W,et al. Oxide properties and stress corrosion cracking behaviour for alloy 600 in leaded caustic solutions at high temperature[J]. Corrosion Science,2011,53(4):1247-1253.
【8】LIU Z Y,HOU Q,LI C T,et al. Correlation between grain boundaries,carbides and stress corrosion cracking of alloy 690TT in a high temperature caustic solution with lead[J]. Corrosion Science,2018,144:97-106.
【9】马明娟,李成涛,张立红. 国产690合金管在碱溶液中的应力腐蚀行为研究[J]. 金属功能材料,2016,23(2):30-34.
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【11】CRUM J R. Stress corrosion cracking testing of inconel alloys 600 and 690 under high-temperature caustic conditions[J]. Corrosion,1986,42(6):368-372.
【12】STAEHLE R W,GORMAN J A. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors:part 1[J]. Corrosion,2003,59(11):931-994.
【13】STAEHLE R W,GORMAN J A. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors:part 2[J]. Corrosion,2004,60(1):5-63.
【14】STAEHLE R W,GORMAN J A. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors:part 3[J]. Corrosion,2004,60(2):115-180.
【15】JACKO R J. Corrosion evaluation of thermally treated alloy 600 tubing in primary and faulted secondary water environments[R]. EPRI NP-6721. Pittsburgh:[s.n.],1990.
【16】KIM S W,KIM H P. Electrochemical noise analysis of PbSCC of alloy 600 SG tube in caustic environments at high temperature[J]. Corrosion Science,2009,51(1):191-196.
【17】IAEA.Stress corrosion cracking in light water reactors:good practices and lessons learned[R]. IAEA Nuclear Energy Series.[S.l.]:[s.n.],2011:29.
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【19】但体纯,王俭秋,韩恩厚,等. 压水堆核电站蒸汽发生器用600合金管在含铅高温碱溶液中的应力腐蚀行为研究[J]. 腐蚀科学与防护技术,2008,20(5):313-316.
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