压水堆核电站加锌水化学技术的研究进展
Research Development of Zinc Water Chemistry in PWRs
摘 要
压水堆（PWR）核电站一回路采用的加锌水化学（ZWC）技术是抑制一回路结构材料腐蚀失效最有效的方法之一。综合分析了ZWC技术在国外PWR核电站的应用概况，加锌对结构材料均匀腐蚀、氧化膜及应力腐蚀等的影响，以及目前研究存在的问题。
加锌水化学
腐蚀
应力腐蚀开裂
氧化膜
pressurized water reactor
zinc water chemistry
corrosion
stress corrosion cracking
oxide film
Abstract
Zinc addition in the primary side circuit of pressurized water reactor (PWR) nudear power plants as zinc water chemistry (ZWC) is one of the most effective methods to mitigate the corrosion of structural materials. The general situation of ZWC application to PWR nudear power plants overseas, the effects of ZWC on general corrosion, stress corrosion cracking and oxide films of structural materials, and the existing problems are summarized.
中图分类号 TG172 DOI 10.11973/fsyfh-201807011
所属栏目 核电设备的腐蚀与防护
基金项目
收稿日期 2017/5/24
修改稿日期
网络出版日期
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引用该论文: HAI Zhengyin,XIN Changsheng,WANG Hui. Research Development of Zinc Water Chemistry in PWRs[J]. Corrosion & Protection, 2018, 39(7): 539
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参考文献
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【28】ANDRESEN P L. Use of primary water chemistry in PWRs to mitigate PWSCC of Ni-Base alloys[C]//Int Conf on Water Chemistry of Nuclear Reactor Systems.[S.l.]:[s.n.],2006.
【2】STAEHLE R W,GORMAN J A. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors:part 1[J]. Corrosion,2003,59:931-994.
【3】STAEHLE R W,GORMAN J A. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors:part 2[J]. Corrosion,2003,59:5-180.
【4】PASTINA B,ISABEY J,HICKEL B. The influence of water chemistry on the radiolysis of the primary coolant water in pressurized water reactors[J]. Journal of Nuclear Materials,1999,264:309-318.
【5】MARBLE W J. BWR radiation field control using zinc injection passivation[R]. EPRI,[S.l.]:[s.n.],1986. 4474.
【6】STABLEFORD H. Experience with zinc injection in european PWRs[R]. EPRI,CA:[s.n.],2002. 1003378.
【7】MASASHI H,SHOICHI O. Effect of zinc addition on cobalt ion accumulation into the corrosion surface of type 304 stainless steel in high-temperature water containing dissolved hydrogen[J]. Zairyo-to-Kankyo,1997,46:565-571.
【8】ZIEMNIAK S E,HANSON M. Zinc treatment effects on corrosion behavior of 304 stainless steel in high temperature,hydrogenated water[J]. Corrosion Science,2006,48:2525-2546.
【9】潘向烽,段正刚. 锌对316L奥氏体不锈钢氧化膜影响的XPS分析[J]. 上海交通大学学报,2014,48(3):417-421.
【10】王力. 加锌对一回路材料氧化膜结构影响及其机理研究[D]. 上海:上海交通大学,2012.
【11】STELLWAG B. The mechanism of oxide film formation on austenitic stainless steels in high temperature water[J]. Corrosion science,1998,40:337-370.
【12】MOHAMED S. Characterization of the oxide films formed at the surface of Ni-base alloys in pressurized water reactors primary coolant by transmission electron microscopy[C]//7th International Symposium on High Temperature Corrosion and Protection of Materials.[S.l.]:[s.n.],2008.
【13】KUANG W,WU X,HAN E H. Influence of dissolved oxygen concentration on the oxide film formed on alloy 690 in high temperature water[J]. Corrosion Science,69:197-204.
【14】SENNOUR M,MARCHETTI L,MARTIN F,et al. A detailed TEM and SEM study of Ni-base alloys oxide scales formed in primary conditions of pressurized water reactor[J]. Journal of nuclear material,2010,402:147-156.
【15】HUA S. Effects of pH and dissolved oxygen on electrochemical behavior and oxide films of 304SS in borated and lithiated high temperature water[J]. Corrosion Science,2012,59:334-342.
【16】HAN G D. Properties of oxide films formed on 316L SS and model alloys with modified Ni,Cr and Si contents in high temperature water[J]. Corrosion Science,2016,in press.
【17】ZHANG Z M. Influence of dissolved oxygen on oxide films of alloy 690TT with different surface status in simulated primary water[J]. Corrosion Science,2011,53:3623-3635.
【18】KUANG W J. The mechanism of oxide film formation on alloy 690 in oxygenated high temperature water[J]. Corrosion Science,2011,53:3853-3860.
【19】KAWAMURA H. The effect of zinc addition to simulated PWR primary water on the PWSCC resistance,crack growth rate and surface oxide films characteristics of prefilmed alloy 600[C]//NACE 1998. Houston:Corrosion,1998:98141.
【20】LIU X H,HAN E H,WU X Q. Effects of pH value on characteristics of oxide films on 316L stainless steel in Zn-injected borated and lithiated high temperature water[J]. Corrosion Science,2014,78:200-207.
【21】LIU X H,HAN E H,WU X Q. Lnfluence of Zn injection on characteristics of oxide film on 304 stainless steel in borated and lithiated high temperature water[J]. Corrosion Science,2011,53:3337-3345.
【22】ESPOSITO J N. The addition of zinc to primary reactor coolant for enhanced PWSCC resistance[C]//Proc 5th Int Symp on Environmental degradation of Materials in Nuclear Power Systems-Water Reactors.[S.l.]:[s.n.],1991:495.
【23】STEPHEN E Z,MICHAEL H. Corrosion behavior of NiCrMo alloy 625 in high temperature,hydrogenated water[J]. Corrosion Science2003,45:1595-1618.
【24】HUANG J B,LI X H,HAN E H,et al. Influence of Zn on oxide films on alloy 690 in borated and lithiated high temperature water[J]. Corrosion Science,2011,53:3254-3261.
【25】BEVERSKOG B. The role of zinc in LWRs[C]//Proc Int Conf on Water Chemistry of Nuclear Reactor Systems. San Francisco:[s.n.],2004:414-426.
【26】LIN C C. Effects of hydrogen water chemistry on radiation field buildup in BWRs[J]. Nuclear Engineering Design,1996,166:31-36.
【27】NORRING K,ENGSTROM J. Initiation of SCC in nickel base alloys in primary PWR environment:studies at Studsvik since mid-1980s[J]. Energy Mater,2008,3:113-118.
【28】ANDRESEN P L. Use of primary water chemistry in PWRs to mitigate PWSCC of Ni-Base alloys[C]//Int Conf on Water Chemistry of Nuclear Reactor Systems.[S.l.]:[s.n.],2006.
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