摘要
在很多核电站的蒸汽发生器中都发现了金属态铅或氧化态铅 ,因而蒸汽发生器传热管的铅诱导 (铅致 )应力腐蚀破裂 (PbSCC)已引起广泛的注意。已证实在压水堆的蒸汽 /水系统 ,特别对管材 ,存在着铅的许多可能的来源。本文介绍了PbSCC的现场事例 ,讨论在压水堆 (PWR)二回路条件 (碱性、酸性和近中性 )
Lead, either in metallic form or the form of lead oxide, is found in the steam generator of many nuclear power plants. The lead induced stress corrosion cracking (PbSCC) has received extensive attention. Many potential sources of lead have been identified in PWR steam water system, mainly at the tube level. In this review, the field occurrence of PbSCC and the mechanisms through which lead affects the SCC susceptibility of nickel alloys under PWR secondary side conditions (caustic, acidic and near neutral) are discussed. Lead induced cracking occurs across the whole feasible range of pH and is the main type of tube degradation for which there is unequivocal evidence that it occurs in the mid range, moderately alkaline pH, a target of secondary water chemistry treatment to minimize general corrosion. However, whether the minor amounts of lead found in practically every steam generator have a critical influence on nickel alloys as distinct from aggravating another underlying degradation mechanism remains unresolved.
出处
《腐蚀与防护》
CAS
2001年第11期483-488,共6页
Corrosion & Protection
基金
国家重点基础研究规划项目 (G19990 6 5 0 )资助
关键词
镍合金
蒸汽发生器
铅致应力腐蚀破裂
二回路水化学
Nickel alloy
Steam generator
Lead induced stress corrosion cracking (PbSCC)
Secondary side water chemistry
