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Oxidation of nickel-base welds 182 and 82 in simulated primary water of pressurised water reactors

机译：压水堆模拟一次水中镍基焊缝182和82的氧化

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摘要

To date, nickel-base welds 182 and 82 used in pressurised water reactors have shown a higher susceptibility to stress corrosion cracking (SCC) during laboratory tests than in power plants. However, the increasing number of cracks reported in American, Swedish and Japanese nuclear power plants on Alloys 182/82 enlightens the need for a predictive initiation model of SCC. Initiation of SCC involves several variables interacting together such as material microstructure and composition, primary water chemistry and loading history. Building such a model requires studying each contribution of individual phenomenon, in order to have a better understanding of the mechanisms involved at a local scale in crack initiation. Before SCC initiation, some grain boundaries exposed to primary water present intergranular oxidation reaching several hundreds of nanometres. The oxide penetration kinetics could be modified by several parameters such as local metallurgy, dissolved hydrogen content of the primary water and mechanical history before oxidation. The grain boundaries affected by oxidation during a tensile test demonstrate a lower resistance to failure compared to 'healthy' grain boundaries. The main objective of this study is to determine key local parameters controlling grain boundary oxidation in order to calibrate an oxidation model which will be integrated to SCC initiation modelling.
机译：迄今为止，在压水反应堆中使用的镍基焊缝182和82与在电厂中相比，在实验室测试中表现出更高的应力腐蚀开裂（SCC）敏感性。但是，美国，瑞典和日本的核电站在182/82合金上报告的裂纹数量不断增加，这激发了对SCC预测启动模型的需求。 SCC的引发涉及几个相互影响的变量，例如材料的微观结构和组成，主要水化学和装料历史。建立这样的模型需要研究每个现象的每个贡献，以便更好地了解局部范围内裂纹萌生的机制。在SCC引发之前，暴露于一次水的某些晶界存在晶间氧化，达到数百纳米。可以通过几个参数来修改氧化物的渗透动力学，例如局部冶金，一次水中溶解氢的含量以及氧化前的机械历史。与“健康”的晶界相比，在拉伸试验中受氧化影响的晶界表现出较低的抗破坏性。这项研究的主要目的是确定控制晶界氧化的关键局部参数，以校准氧化模型，该模型将被整合到SCC引发模型中。

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