Assessing the risk of under-deposit chloride-induced stress corrosion cracking in austenitic stainless steel nuclear waste containers
Assessing the risk of under-deposit chloride-induced stress corrosion cracking in austenitic stainless steel nuclear waste containers
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DOI：
10.1179/1743278214y.0000000204
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发表时间：
2014-09-01
影响因子：
1.8
通讯作者：
Engelberg, D. L.
中科院分区：
文献类型：
--
作者：
Cook, A. B.;Lyon, S. B.;Engelberg, D. L.
本文对304L和316L奥氏体不锈钢中通常被称为大气氯化物诱发应力腐蚀开裂（AISCC）现象的发生进行了简要总结；这些材料目前用来制造储存英国中间水平核废料的容器。简要概述了局部腐蚀现象（点蚀或缝隙腐蚀）和应力腐蚀开裂之间的关系，这些关系是在含氯化物环境中浸没的条件下观察到的。本文还讨论了环境变量（如相对湿度、温度和氯离子沉积密度）对AISCC发展的影响，以及将实验室调查数据外推到实际情况的潜在困难。还简要讨论了关于制定更准确地反映实际储存情况下行为的实验室规程的建议，包括采用加速测试方法的可能性。
This paper provides a short summary of investigations that have focused on the occurrence of the phenomenon that is commonly referred to as atmospheric chloride-induced stress corrosion cracking (AISCC) in types 304L and 316L austenitic stainless steels; the materials from which storage containers for the UK's intermediate level nuclear waste are currently fabricated. A brief overview of the relationship between localised corrosion phenomena (pitting or crevice corrosion) and stress corrosion cracking from observations derived under conditions of immersion in chloride-containing environments is provided. The impact of environmental variables such as the relative humidity, temperature and chloride deposition density on the development of AISCC and potential difficulties in extrapolating data derived from laboratory investigations to an in-store situation are also discussed. Proposals for the development of laboratory protocols that may more accurately reflect behaviour in an actual storage situation, including the possibility of employing accelerated testing methods, are also briefly addressed.