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核电厂不锈钢覆面焊接模拟件腐蚀行为研究
引用本文:王宇欣,胡月飞,高宇,郭城湘,左景辉.核电厂不锈钢覆面焊接模拟件腐蚀行为研究[J].核动力工程,2022,43(3):214-219.
作者姓名:王宇欣  胡月飞  高宇  郭城湘  左景辉
作者单位:1.中国核电工程有限公司,北京,100840
摘    要:对3种核电厂乏燃料水池不锈钢覆面材料S32205、S32101和S30403的焊接模拟件,在H3BO3浓度2500 mg/L、SO42?浓度1500 mg/L、Cl?浓度5%、pH值5.0、温度80℃、饱和氧的条件下浸泡6个月,对比研究其腐蚀行为。结果发现:S30403焊接模拟件在焊接节点和缝隙附近出现了大量的氯致应力腐蚀裂纹;S32101焊接模拟件出现了腐蚀坑,在焊接节点和缝隙附近腐蚀尤其严重;S32205焊接模拟件腐蚀最轻,试件表面未发现腐蚀坑及裂纹。研究表明:3种材料模拟件的耐腐蚀性规律为:S32205>S32101>S30403。S32205具有良好的综合力学性能和耐腐蚀性能,是一种理想的改进型水池覆面材料。 

关 键 词:不锈钢覆面    焊接模拟件    腐蚀行为    S32205
收稿时间:2021-07-19

Research on Corrosion Behavior of Stainless Steel Cladding Welding Simulator in Nuclear Power Plant
Affiliation:1.China Nuclear Power Engineering Co., Ltd., Beijing, 100840, China2.Institute of Metal Research Chinese Academy of Science, Shenyang, 110016, China
Abstract:The corrosion behavior of the welding simulators of three stainless steel cladding materials S32205, S32101 and S30403 in spent fuel pool of nuclear power plant was studied by soaking them for 6 months under the conditions of H3BO3 concentration of 2500 mg/L, SO42? concentration of 1500 mg/L, Cl? concentration of 5%, pH value of 5.0, temperature of 80 ℃ and saturated oxygen. The results show that a large number of chlorine induced stress corrosion cracks appear near the welding joints and gaps of S30403 welding simulator; S32101 welding simulator has corrosion pits, especially near the welding joints and gaps; S32205 welding simulator has the lightest corrosion, and no corrosion pits and cracks are found on the surface of the test piece. The research shows that the corrosion resistance law of the three material simulator is: S32205>S32101>S30403. S32205 has good comprehensive mechanical properties and corrosion resistance, is an ideal improved pool cladding material. 
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