期刊文献+

压水堆腐蚀产物行为影响因素及模型综述

Review of Factors Affecting Corrosion Products Behavior and Related Models
下载PDF
导出
摘要 压水堆一回路腐蚀产物沉积对反应堆的安全、稳定运行有重要影响。迄今为止,针对腐蚀产物行为已开展了广泛研究。本文概述了腐蚀产物行为的主要影响因素,包括水化学条件、热通量、冷却剂流速等。合适的水化学条件,如pH控制在7.4附近、溶解H浓度在25~50 cm^(3)/kg H_(2)O之间,会降低腐蚀产物生成量。热通量、冷却剂流速对腐蚀产物沉积也有不可忽视的影响。另外,对具有代表性的腐蚀产物行为预测模型及燃料元件表面腐蚀产物沉积影响模型进行了介绍,并对今后腐蚀产物行为的进一步研究提出了建议。 The corrosion product deposits in the primary circuit of PWR has an important impact on the safe and stable operation of the reactor. So far, a large number of studies about corrosion product behaviors have been investigated. However, considering the inconsistency of experimental conditions and the complexity of the formation, migration and deposition mechanism of corrosion products, no definite conclusions have been drawn in many research directions. In this paper, the influence factors affecting the behavior of corrosion products,such as water chemistry condition, heat flux and coolant flow rate are summarized. Appropriate water chemistry conditions, such as pH around 7.4 and dissolved H concentration between 25-50 cm^(3)/kg H_(2)O, will reduce the generation of corrosion products. In addition, the effects of the heat flux and the coolant flow rate on the deposition of corrosion products cannot be ignored. In addition, several representative codes for predicting the behaviors of corrosion product deposits and some models for predicting the influence of corrosion product deposits on the operation of reactors are introduced. Several constructive suggestions for the further research about corrosion product deposits are put forward.
作者 吉利 卢川 段振刚 沈媛 张萌 周羽 矫彩山 侯洪国 高杨 JI Li;LU Chuan;DUAN Zhengang;SHEN Yuan;ZHANG Meng;ZHOU Yu;JIAO Caishan;HOU Hongguo;GAO Yang(College of Nuclear Science and Technology,Harbin Engineering University,Harbin of Heilongjiang Prov.150001,China;National Key Laboratory on Reactor System Design Technology,Nuclear Power Institute of China,Chengdu of Sichuan Prov.610041,China)
出处 《核科学与工程》 CAS CSCD 北大核心 2022年第6期1432-1440,共9页 Nuclear Science and Engineering
关键词 腐蚀产物 水化学条件 计算代码 传热模型 CRUD Water chemistry Computer code Heat transfer model
  • 相关文献

参考文献1

二级参考文献20

  • 1Burke M A. Materials selection and validation for light water reactor electricity generating capacity sustainabil- ity[A], 5th IMR Symposium on Materials Science and Engineering: Materials and Reliability in Nuclear Power Plants[C]. China, Shenyang: 2009.
  • 2Nakagawa T, Totsuka N, Terachi T, et al. Influence of dis- solved hydrogen on oxide film and PWSCC of Alloy 600 in PWR primary water[J]. J. Nucl. Sci. Technol., 2003, 40(1): 39-43.
  • 3Terachi T, Fujii K, Arioka K. Microstructure characteriza- tion of SCC crack tip and oxide film for SUS 316 stainless steel in simulated PWR primary water at 320 ℃ [J]. J. Nucl. Sci. Technol., 2003, 42(2): 225-232.
  • 4Tostuka N, Szklarska-Smialowska Z. Hydrogen induced IGSCC of two unsensitized austenitic stainless steels in high-temperature water[J]. Corrosion, 1988, 44(2): 124- 126.
  • 5Arioka K. Effect of temperature hydrogen and boric acid concentration on IGSCC susceptibility of annealed 316 stainless steel[A]. Proc. Int. Symp. Fontevraud 5[C]. 2002:23-27.
  • 6Arioka K, Yamada T, Takumi T. Influence of boric acid, hydrogen concentration and grain boundary carbide on IGSCC behaviors of SUS 316 under PER primary wa- ter[A]. Proc. llth Int. Conf. Environmental Degrada- tion of Materials in Nuclear Systems [C]. Stevenson, 2003: 10-14.
  • 7Arioka K, Yamada T. Intergranular stress corrosion crack- ing behavior of austenitic stainless steels in hydrogenated high-temperature water[J]. Corrosion, 2006, 62(1): 74-83.
  • 8Qiu Y B, Shoji T, Lu Z P. Effect of dissolved hydrogen on the electrochemical behaviour of alloy 600 in simulated PWR water at290 ℃ [J]. Corros. Sci., 2011, 53:1983-1989.
  • 9Hou J, Peng Q J, Kuniya J, et al. Effect of hydrogen in Inconel Alloy 600 on corrosion in high temperature oxy- genated water[J]. Corros. Sci., 2010, 52:1098-1101.
  • 10Terachi T, Totsuka N, Yamada T, et al. Influence of dis- solved hydrogen on structure of oxide film on alloy 600 formed in primary water of pressurized water reactors[J].J. Nucl. Sci. Technol., 2003, 40(7): 509-516.

共引文献9

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