高温模拟压水堆一回路水中SO42-对690TT镍基合金SCC敏感性的影响
Effect of SO2-4 on SCC Susceptibility of Nickel-Based Alloy 690TT in Simulated PWR Primary Water at High Temperature
摘 要
采用慢应变速率试验(SSRT)研究了310℃模拟压水堆一回路水中硫酸根离子(SO42-)含量对690TT镍基合金应力腐蚀开裂(SCC)敏感性的影响。结果表明:690TT镍基合金试样的断口附近均出现了颈缩,在SO42-含量较低的模拟压水堆一回路水中,690TT镍基合金试样断口大多呈剪切状,应力腐蚀敏感性低;当SO42-质量分数达到1 500 μg/kg时,断口边缘局部出现穿晶裂纹,高含量的SO42-使690TT镍基合金的应力腐蚀开裂敏感性提高。
蒸汽发生器传热管
690TT镍基合金
应力腐蚀开裂
高温水
硫酸根
pressurized water reactor (PWR)
steam generator heat exchange tube
nickel-based alloy 690TT
stress corrosion cracking
high temperature water
sulfate
Abstract
The effect of SO42- concentration on stress corrosion cracking (SCC) susceptibility of nickel-based alloy 690TT in simulated pressurized water reactor (PWR) primary water was investigated by slow strain rate testing (SSRT) at 310 ℃. The results show that necking occurred near the fracture of the nickel-based alloy 690TT samples. In the PWR primary water containing low concentration of SO42-, most fractures of the nickel-based alloy 690TT samples were shear-like, and the stress corrosion susceptibility of the alloy was low. When the mass fraction of SO42- reached 1 500 μg/kg, transgranular cracks occurred at the localized zones of fracture edge, which means high concentration of SO42- increased the SCC susceptibility of nickel-based alloy 690TT.
中图分类号 TG172 DOI 10.11973/fsyfh-202208013
所属栏目 试验研究
基金项目 中国广核集团尖峰计划(R-2020SZSO53TF);国家自然科学基金(51771107)
收稿日期 2022/2/18
修改稿日期
网络出版日期
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引用该论文: LIN Genxian,SONG Lijun,LIU Canshuai,CUI Tongming,XU Xinhe,LYU Zhanpeng. Effect of SO2-4 on SCC Susceptibility of Nickel-Based Alloy 690TT in Simulated PWR Primary Water at High Temperature[J]. Corrosion & Protection, 2022, 43(8): 65
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参考文献
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【2】CHEN J J,LU Z P,MENG F J,et al.The corrosion behaviour of alloy 690 tube in simulated PWR secondary water with the effect of solid diffusing hydrogen .Journal of Nuclear Materials,2019,517:179-191.
【3】LU Z P,CHEN J J,SHOJI T,et al.Characterization of microstructure,local deformation and microchemistry in Alloy 690 heat-affected zone and stress corrosion cracking in high temperature water .Journal of Nuclear Materials,2015,465:471-481.
【4】SHOJI T, LU Z P, YAMAZAKI S. The effect of strain-hardening on PWSCC of nickel-base Alloys 600 and 690 //Proceedings of the 14th Conference on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors. :, 2009.
【5】唐占梅,孟凡江,张平柱,等.核电用690合金传热管抗苛性应力腐蚀性能评价 .稀有金属材料与工程,2019,48(11):3541-3547.
【6】ARIOKA K, YAMADA T, MIYAMOTO T, et al. SCC Initiation of CW Alloy TT690 and Alloy 600 in PWR water //Proceedings of the 17th International Conference on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors. :, 2015:1-15.
【7】但体纯,吕战鹏,王俭秋,等.690合金在高温水中的应力腐蚀裂纹扩展行为 .金属学报,2010,46(10):1267-1274.
【8】李成涛,宋利君,任爱,等.690合金在核电一回路水环境的应力腐蚀行为 .哈尔滨工程大学学报,2013,34(11):1465-1470.
【9】吴恋恋,张乐福,潘向烽,等.核电厂蒸汽发生器管材800与690合金应力腐蚀性能 .腐蚀与防护,2014,35(1):47-51.
【10】夏小峰,吕战鹏,陈俊劼,等.预形变及模拟压水堆一回路水中预浸泡对690合金拉伸性能的影响 .腐蚀与防护,2015,36(2):170-176.
【11】TAN J B,WU X Q,HAN E H,et al.Corrosion fatigue behavior of Alloy 690 steam generator tube in borated and lithiated high temperature water .Corrosion Science,2014,89:203-213.
【12】王光辉,彭君,袁义帆,等.硫酸根离子和电极电位对异材焊接件A508/52M在高温水中应力腐蚀破裂的影响 .理化检验(物理分册),2013,49(6):357-361,366.
【13】夏大海,LUO J L.690合金在300 ℃含硫模拟碱性水化学中的腐蚀行为 .物理化学学报,2015,31(3):467-475.
【14】林震霞,邱绍宇,肖军,等.Cl-和Cu2+对国产690合金应力腐蚀性能的影响 .核动力工程,2015,36(1):50-54.
【15】夏大海,宋诗哲,王俭秋,等.690和800合金在高温高压水中硫致腐蚀失效研究进展 .金属学报,2017,53(12):1541-1554.
【16】ANDRESEN P L.Effects of temperature on crack growth rate in sensitized type 304 stainless steel and alloy 600 .Corrosion,1993,49(9):714-725.
【17】ANDRESEN P L,BRIANT C L.Environmentally assisted cracking of types 304L/316L/316NG stainless steel in 288 ℃ water .Corrosion,1989,45(6):448-463.
【18】YANG W,LU Z P,HUANG D L,et al.Caustic stress corrosion cracking of nickel-rich,chromium-bearing alloys .Corrosion Science,2001,43(5):963-977.
【19】MULFORD S J,TROMANS D.Crevice corrosion of nickel-based alloys in neutral chloride and thiosulfate solutions .Corrosion,1988,44(12):891-900.
【20】XIA D H,SONG S Z,ZHU R K,et al.A mechanistic study on thiosulfate-enhanced passivity degradation of Alloy 800 in chloride solutions .Electrochimica Acta,2013,111:510-525.
【21】CUI T M,XU X H,MA J R,et al.Effects of composition and microstructure on oxidation and stress corrosion cracking susceptibility of stainless steel claddings in hydrogenated PWR primary water .Journal of Nuclear Materials,2021,553:153057.
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