<strong>904L</strong>超级奥氏体不锈钢在模拟核电一回路环境中的腐蚀行为研究

doi:10.11902/1005.4537.2023.230

中国腐蚀与防护学报

2024, Vol. 44

Issue (3): 716-724 CSTR: 32134.14.1005.4537.2023.230 DOI: 10.11902/1005.4537.2023.230

研究报告

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904L超级奥氏体不锈钢在模拟核电一回路环境中的腐蚀行为研究

李禅¹, 王庆田², 杨承刚¹, 张宪伟³, 韩冬傲¹, 刘雨薇¹, 刘智勇³(

)

1.生态环境部核与辐射安全中心北京 100082
2.中国核动力研究设计院　核反应堆系统设计技术重点实验室成都 610213
3.北京科技大学国家材料腐蚀与防护科学数据中心北京 100083

Corrosion Behavior of 904L Super-austenitic Stainless Steel in Simulated Primary Water in Nuclear Power Plants

LI Chan¹, WANG Qingtian², YANG Chenggang¹, ZHANG Xianwei³, HAN Dongao¹, LIU Yuwei¹, LIU Zhiyong³(

)

1. Nuclear and Radiation Safety Center, Ministry of Ecology and Environment, Beijing 100082, China
2. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China
3. National Materials Corrosion and Protection Data Center, University of Science and Technology Beijing, Beijing 100083, China

引用本文:

李禅, 王庆田, 杨承刚, 张宪伟, 韩冬傲, 刘雨薇, 刘智勇. 904L超级奥氏体不锈钢在模拟核电一回路环境中的腐蚀行为研究[J]. 中国腐蚀与防护学报, 2024, 44(3): 716-724.
Chan LI, Qingtian WANG, Chenggang YANG, Xianwei ZHANG, Dongao HAN, Yuwei LIU, Zhiyong LIU. Corrosion Behavior of 904L Super-austenitic Stainless Steel in Simulated Primary Water in Nuclear Power Plants[J]. Journal of Chinese Society for Corrosion and protection, 2024, 44(3): 716-724.

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摘要:

采用动电位极化曲线、电化学阻抗谱(EIS)以及U形弯浸泡实验，研究了原始、敏化和固溶等3种微观组织状态下904L超级奥氏体不锈钢在模拟核电一回路环境中的电化学和应力腐蚀开裂(SCC)行为及机理。结果表明：904L不锈钢在模拟核电一回路中的腐蚀过程基本由电化学活化控制。温度对原始、敏化和固溶等组织状态下的904L不锈钢的耐腐蚀性能有很大影响，随温度升高，电化学反应极化电阻降低，钝化区变窄，腐蚀电位下降，3种组织状态的904L不锈钢耐蚀性均急剧降低。3种组织状态的904L不锈钢在模拟核电一回路环境中均存在一定SCC敏感性。表面腐蚀产物膜内层为均匀较薄的黑色腐蚀产物，外层为尺寸较大的颗粒状白色腐蚀产物。敏化组织的904L不锈钢SCC敏感性最高，固溶处理能降低其SCC敏感性。

关键词 ：超级奥氏体不锈钢, 应力腐蚀, 电化学特性, 一回路, 核电

Abstract：

In this work, the electrochemical properties and stress corrosion cracking (SCC) behavior of 904L super-austenitic stainless steel with various kinds of microstructure in simulated primary water were studied through potentiodynamic polarization curve measurement, electrochemical impedance spectroscopy (EIS) and U-bend immersion tests. The results show that the corrosion process of 904L stainless steel in simulated primary water is completely controlled by electrochemical reaction. Temperature has a strong influence on the corrosion resistance of 904L stainless steel. With the increase of temperature, the polarization resistance decreases; the passive range narrows down; corrosion potential shifts negatively, and corrosion resistance declines sharply. U-bend immersion test results prove that 904L stainless steel with the three kinds of microstructure has certain SCC susceptibility in simulated primary water. The corrosion products exert a two-layered structure, where the inner layer is uniform and thin black corrosion product, and the outer layer is granular and coarse white corrosion products. Among the three kinds of microstructure, the sensitized 904L stainless steel presents the highest SCC susceptibility, while solid solution treatment can decrease SCC susceptibility.

Key words： super-austenitic stainless steel stress corrosion cracking electrochemical behavior primary water nuclear power plant

收稿日期: 2023-07-24 32134.14.1005.4537.2023.230

ZTFLH:

TG174.2

基金资助:国家自然基金(U22B2065);核反应堆系统设计技术重点实验室开放课题

通讯作者: 刘智勇，E-mail：liuzhiyong7804@126.com，研究方向为材料应力腐蚀行为与机理、局部腐蚀电化学监测检测技术

Corresponding author: LIU Zhiyong, E-mail: liuzhiyong7804@126.com

作者简介: 李禅，男，1981年生，硕士，高级工程师

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https://www.jcscp.org/CN/10.11902/1005.4537.2023.230 或 https://www.jcscp.org/CN/Y2024/V44/I3/716

表1 实验用904L不锈钢的力学性能

图1 U形弯浸泡试样尺寸

图2 904L不锈钢金相照片及EBSD结果

图3 3种处理态904L不锈钢的XRD谱图

图4 原始和不同热处理态的904L不锈钢在不同温度下测试溶液中的极化曲线

表2 3种不同处理态904L不锈钢在不同温度下测试溶液中的极化曲线拟合结果

图5 3种不同处理态的904L不锈钢在不同温度下测试溶液中的阻抗谱

图6 阻抗谱等效电路图

表3 3种不同组织904L不碳钢在不同温度环境下阻抗拟合结果

图7 不同处理态904L不锈钢U弯样品在溶液中浸泡不同时间后的宏观形貌

图8 不同处理态904L不锈钢U弯样品在测试溶液中浸泡不同时间后的微观形貌

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