核电厂水池覆面用不锈钢钢板在硼酸水溶液中的点蚀行为
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  • 英文篇名:Pitting Corrosion Behavior of Stainless Steel Plate Used for Steel Liner of Nuclear Power Plant in Boric Acid Solution
  • 作者:郑越 ; 雷欣 ; 崔岚 ; 张洪军
  • 英文作者:ZHENG Yue;LEI Xin;CUI Lan;ZHANG Hongjun;CNNC China Nuclear Power Engineering Co.,Ltd.;
  • 关键词:钢覆面 ; Cl- ; SO42- ; 点蚀电位 ; 再钝化电位
  • 英文关键词:steel liner;;Cl-;;SO42-;;pitting corrosion potential;;repassivation potential
  • 中文刊名:FSYF
  • 英文刊名:Corrosion & Protection
  • 机构:中国核电工程有限公司;
  • 出版日期:2017-07-15
  • 出版单位:腐蚀与防护
  • 年:2017
  • 期:v.38;No.333
  • 语种:中文;
  • 页:FSYF201707001
  • 页数:6
  • CN:07
  • ISSN:31-1456/TQ
  • 分类号:5-9+35
摘要
采用电化学方法研究了温度、Cl~-以及SO_4~(2-)含量对不锈钢板S30403、S32101和S32205在硼酸溶液中点蚀行为的影响。结果表明:3种材料的点蚀电位(Eb)和再钝化电位(Er)均随Cl~-含量的升高而降低,S32205不锈钢的点蚀电位和再钝化电位普遍高于S32101和S30403不锈钢的;存在临界温度(约60℃),当温度高于临界温度,S32205不锈钢的点蚀电位大幅降低,再钝化电位的临界温度介于40~60℃;SO_4~(2-)含量对3种材料点蚀电位和再钝化电位的影响不明显。S32205不锈钢的耐点蚀性能优于S32101和S30403不锈钢的,而S32101和S30403不锈钢的耐点蚀性能相当。
        The effects of temperature,Cl~-content and SO_4~(2-)content on pitting behavior of S30403,S32101 and S32205stainless steel plates in boric acid solution were studied by electrochemical methods.The results show that pitting potential(Eb)and repassivation potential(Er)of those three materials declined when increasing the content of Cl~-,pitting potential and repassivation potential of S32205 stainless steel were higher than those of S32101 and S30403stainless steels.A critical temperature(about 60 ℃)existed,when the temperature was higher than the critical temperature,the pitting potential decreased obviously.Critical temperature for repassivation potential was in the range of 40~60 ℃.The effect of the content of SO_4~(2-)on pitting potential and repassivation potential for three materials was little.The pitting corrosion resistance of S32205 stainless steel is more excellent than that of S30403 and S32101 stainless steels in different experimental conditions,while the pitting corrosion resistance of S30403 and S32101 stainless steels is equivalent.
引文
[1]陈超,袁炜,郑越,等.核电站水池钢覆面耐应力腐蚀行为及设计改进[J].核工程研究与设计,2014,35(1):37-41.
    [2]0401XPTRXTS01反应堆换料水池和乏燃料水池冷却和处理系统手册[S].核工业第二研究设计院,2008.
    [3]操丰,方江,唐世延,等.核电厂换料水池304L不锈钢覆面开裂原因分析[J].核动力工程,2014,35(2):150-153.
    [4]RCC-M M3407 Design and construction rules for mechanical components of PWR nuclear islands[S].France:French Association of Nuclear Standard,2007.

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