Mechanisms of Stress Corrosion Cracking

Bernadett Spisák, S. Szávai
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引用次数: 18

Abstract

Stress corrosion cracking (SCC) even nowadays is the cause of significant service failures, it can occur in almost any type of components of the chemical industry such as steam generator tubes, pressurizer instrument penetrations and heater sleeves, control rod drive mechanism (CRDM) nozzles, heat exchangers [1]-[6]. One of the most recent major accident happened in 2009, where a 50-foot-tall highpressure vessel ruptured, resulting in one fatality and one injury of the public. Based on the review of the National Institute of Standards and Technology the failure was caused by the combination of stress corrosion cracking and a reduction in material toughness during service [6]. In case of existing nuclear power plants the stress corrosion cracking counts as one of the important ageing degradations. For stress corrosion to occur three indispensable factors have to be present, which are the tensile stress, the environment and the susceptible material. If changes are made in any of these factors then the susceptibility to SCC often can be eliminated or reduced. The tensile stress can originate from residual stresses, operational loadings, the structural and metallurgical factors includes the degree of grain size, thermal treatment, cold work, and finally the environment factors are resulted from the water chemistry, the operating temperature [1]. However this type of failure is sudden and difficult to predict and also material properties may change with time or due to material processing. Therefore the right way of prediction and modelling of SCC is still a vital research area. In this article the different type of SCC mechanisms are presented, the ones used in the nuclear industry in more details.
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应力腐蚀开裂机理
应力腐蚀开裂(SCC)即使在今天也是造成重大服务故障的原因,它几乎可以发生在化学工业的任何类型的部件中,如蒸汽发生器管,稳压器仪表渗透和加热器套管,控制棒驱动机构(CRDM)喷嘴,热交换器[1]-[6]。最近的一次重大事故发生在2009年,当时一个50英尺高的高压容器破裂,导致一人死亡,一人受伤。根据美国国家标准与技术研究院的审查,该失效是由应力腐蚀开裂和使用过程中材料韧性降低共同引起的[6]。在现有的核电站中,应力腐蚀开裂是重要的老化退化之一。应力腐蚀的发生必须有三个不可缺少的因素,即拉应力、环境和易感材料。如果这些因素中的任何一个发生了变化,那么对SCC的易感性通常可以消除或减少。拉伸应力可以来源于残余应力、操作载荷,结构和冶金因素包括晶粒度、热处理、冷加工,最后是环境因素,包括水化学、操作温度[1]。然而,这种类型的失效是突然的,难以预测的,而且材料的性能可能随着时间的推移或由于材料的加工而改变。因此,正确地预测和建模SCC仍然是一个重要的研究领域。本文介绍了不同类型的SCC机制,并详细介绍了核工业中使用的SCC机制。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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