期刊文献+

压水堆条件下锌对690合金表面氧化膜的影响 被引量:3

Zinc Treatment Effects on Corrosion Behavior of Alloy 690 and the Mechanism in PWR Environment
下载PDF
导出
摘要 模拟压水堆一回路加锌水环境,对镍基690合金在加锌浓度为10μg/kg的320℃,15.20 MPa溶液中进行了1000 h的腐蚀试验。采用XPS深度分析法对试样氧化膜进行分析。结果表明,锌能有效地降低690合金的均匀腐蚀速率,加锌后氧化膜形貌和成分都有了明显改变,氧化膜厚度变薄。 Zinc primary coolant addition of zinc, morphology and addition effects on general corrosion of Nickel- with 10 μg/kg zinc addition at 320 ℃, 15. 20 base Alloy 690 were investigated in simulated PWR MPa for 1000 h. The results show that with the ively reduced. The surface oxide film is thinner, the changed.
出处 《腐蚀与防护》 CAS 北大核心 2012年第12期1042-1044,1090,共4页 Corrosion & Protection
基金 国家科技重大专项(2008ZX06004)
关键词 压水堆 一回路 加锌 均匀腐蚀 PWR primary loop zinc addition general corrosion
  • 相关文献

参考文献8

  • 1Experience with zinc injection in European PWRs[R]. Palo Alto CA: EPRI, 2002. 1003378.
  • 2Chemistry UPdate[R]. Palo Alto CA:EPRI, 1018084, 2008.
  • 3刘侠和,吴欣强,韩恩厚.轻水堆结构材料在加锌水中的腐蚀行为研究现状与进展[J].腐蚀科学与防护技术,2011,23(4):287-292. 被引量:7
  • 4Machet A,Galtayries A, Marcus P, et al. XPS study of oxides formed on nickel-base alloys in high temperature and high-pressure water [C]//Surf Interface Anal, 2002 :197-200.
  • 5Stellwag B. The mechanism of oxide film formation on austenitic stainless steels in high temperature water [J]. Corrosion Science,1998,40(3):337-370.
  • 6Combrade P, Scott P M, Foucault M, et al. Oxidation of Ni base alloys in PWR water:oxide layers and asso- ciated damage to the base metal[C]//Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System- Water Reactors, 2005 : 883- 890.
  • 7Lister D H. Mechanisms of zinc interaction with oxide films in high-temperature water[C]//Presentation at EPRI Meeting, Toronto Ontario Canada, 2004 : 26-28.
  • 8乔培鹏,张乐福,刘瑞芹,姜苏青,朱发文.压水堆条件下锌对奥氏体不锈钢腐蚀性能的影响[J].原子能科学技术,2010,44(6):690-693. 被引量:10

二级参考文献55

  • 1ALTO P.Overview report on zinc addition in pressurized water reactors-2004,CA:1009568[R].South Africa:EPRI,2004.
  • 2ALTO P.Chemistry update,CA:1018084[R].South Africa:EPRI,2008.
  • 3OGAWA N,NAGATA T,YAMADA M,et al.Verification test for radiation exposure reduction effect and material integrity on PWR primary system by zinc injection[C] ∥Proc.8th Internal.Conf.on Water Chemistry of Nuclear Power Systems.Kashiwazaki,Japan:[s.n.] ,1998:329.
  • 4PASTINA 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,1999,64:309-318.
  • 5CHEN P C,LEE M K.Zinc oxide nanostructures prepared by liquid phase deposition[D].Taiwan,China:Department of Electrical Engineering,National Sun Yat-Sen University,2006.
  • 6STALLWAG B.The mechanism of oxide film formation on austenitic stainless steels in high temperature water[J].Corrosion Science,1998,40(2-3):337-370.
  • 7ZIEMNIAK S E,HANSON M.Zinc treatment effects on corrosion behavior of 304 stainless steel in high temperature,hydrogenated water[J].Corrosion Science,2006,48:2 525-2 546.
  • 8Matsuura M, Aoki H, Tsukamoto H, et al. Application of zinc injection to reduce radiation sources at takahama unit 4 [A]. Int. Congress on Advances in Nuclear Power Plants[C]. Shinjuku Tokyo: Curran Associates Inc, 2009: 309.
  • 9熊书华,朱志平,荆玲玲等.压水堆核电站一回路加锌原理及其工艺[A].电厂化学2009学术年会暨中国电厂化网2009高峰论坛会议论文集[C].武汉,2009:81.
  • 10Cubicciotti D. Potential-pH diagrams for alloy-water sys- tems under LWR conditions [J]. J. Nucl. Mater., 1993, 201: 176.

共引文献13

同被引文献13

  • 1HARROD D,GOLD R,JACKO R. Alloy optimization for PWR steam generator heat-transfer tubing [J]. Journal of the Minerals, Metals and Materials Society, 2011,53(7) :14-17.
  • 2HUA 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.
  • 3MACHET A, GALTAYRIES A, MARCUS P, et al. XPS study of oxides formed on nickel-base alloys in high-temperature and high-pressure water[J]. Surface and interface Analysis, 2002,34(1) : 197-200.
  • 4STELLWAG B. The mechanism of oxide film forma- tion on austenitic stainless steels in high temperature water[J]. Corrosion Science, 1998,40 : 337-370.
  • 5ROBERTSON J. The mechanism of high temperature aqueous corrosion of stainless steels[J]. Corrosion Sci- ence, 1991,32 (4) : 443-465.
  • 6Junbo Huang,Xiahe Liu,En-Hou Han,Xinqiang Wu.Influence of Zn on oxide films on Alloy 690 in borated and lithiated high temperature water[J].Corrosion Science.2011(10)
  • 7S.E. Ziemniak,M. Hanson.Zinc treatment effects on corrosion behavior of 304 stainless steel in high temperature, hydrogenated water[J].Corrosion Science.2005(9)
  • 8S.E. Ziemniak,M. Hanson.Corrosion behavior of 304 stainless steel in high temperature, hydrogenated water[J].Corrosion Science.2002(10)
  • 9P Stefanov,D Stoychev,M Stoycheva,Ts Marinova.XPS and SEM studies of chromium oxide films chemically formed on stainless steel 316 L[J].Materials Chemistry and Physics.2000(2)
  • 10姜苏青,张乐福.锌对镍基690合金均匀腐蚀影响的XPS分析[J].原子能科学技术,2012,46(3):268-271. 被引量:4

引证文献3

二级引证文献5

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部