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机构地区:[1]中广核工程有限公司,广东深圳518124 [2]环境保护部核与辐射安全中心,北京100082
出 处:《核动力工程》2014年第6期176-179,共4页Nuclear Power Engineering
摘 要:某核电机组堆芯测量系统(RIC)手动阀和密封组件被误用四氯乙烯进行清洗。而该部件为奥氏体不锈钢,由于四氯乙烯热解过程中会导致氯离子Clˉ的产生,存在Clˉ致应力腐蚀风险。通过分析手动阀和密封组件的残留Clˉ含量、运行温度以及冷却剂中的氧含量,认为残留的Clˉ含量不会导致手动阀和密封组件在服役过程中发生应力腐蚀。RIC manual valves and seal assemblies made of austenitic stainless steel were wrongly degreased with tetrachloroethylene by the manufacturer. Chloride ions (Cl^-) were produced during the pyrolysis of tetrachloroethylene, leading to the risk of stress corrosion cracking (SCC) due to the remaining Cl^-. The research shows that the Cr-Ni austenitic stainless steel becomes more sensitive to the stress corrosion cracking as the Cl^-content increases. Increasing temperature and oxygen (0) content can accelerate the SCC of austenitic stainless steel caused by Cl^-. After the analysis of the remaining Cl^- content in the manual valves and seal assemblies, operating temperature and oxygen content in the coolant, it is considered that the remaining Cl^- will not cause SCC during service of manual valves and seal assemblies. In addition, the pyrolysis of tetrachloroethylene under vacuum and abrasive blasting of surfaces can decrease Cl^- observably.
关 键 词:手动阀和密封组件 奥氏体不锈钢 氯离子(Clˉ) 应力腐蚀开裂(SCC)
分 类 号:TL341[核科学技术—核技术及应用]
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