高温模拟压水堆一回路水中SO_(4)^(2-)对690TT镍基合金SCC敏感性的影响  

Effect of SO_(4)^(2-) on SCC Susceptibility of Nickel-Based Alloy 690TT in Simulated PWR Primary Water at High Temperature

作　　者：林根仙[1] 宋利君[1] 刘灿帅 崔同明 许鑫和 吕战鹏[2] LIN Genxian;SONG Lijun;LIU Canshuai;CUI Tongming;XU Xinhe;LYU Zhanpeng(Suzhou Nuclear Power Research Institute,Suzhou 215004,China;Institute of Materials,School of Materials Science and Engineering,Shanghai University,Shanghai 200072,China)

机构地区：[1]苏州热工研究院有限公司,苏州215004 [2]上海大学材料科学与工程学院材料研究所,上海200072

出　　处：《腐蚀与防护》2022年第8期65-69,共5页Corrosion & Protection

基　　金：中国广核集团尖峰计划(R-2020SZSO53TF);国家自然科学基金(51771107)。

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(SO_(4)^(2-))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SO_(4)^(2-)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SO_(4)^(2-)质量分数达到1500μg/kg时,断口边缘局部出现穿晶裂纹,高含量的SO_(4)^(2-)使690TT镍基合金的应力腐蚀开裂敏感性提高。The effect of SO_(4)^(2-)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 SO_(4)^(2-),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 SO_(4)^(2-) reached 1500μg/kg,transgranular cracks occurred at the localized zones of fracture edge,which means high concentration of SO_(4)^(2-)increased the SCC susceptibility of nickel-based alloy 690TT.

关 键 词：压水堆核电站 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 

分 类 号：TG172[金属学及工艺—金属表面处理]