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Effect of thermal ageing on creep and oxidation behaviour of Type 316H stainless steel

机译：热时效对316H型不锈钢蠕变和氧化行为的影响

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摘要

The UK has unique experience in operating high temperature civil nuclear power systems, known as advanced gas cooled reactors (AGRs). One of the primary challenges for extending the lifetime of the AGR power stations is to understand the interaction that occurs between the AGR CO2 environment and creep-fatigue cracking behaviour. This is one of the life limiting degradation mechanisms for steel components within the reactor pressure vessel. This paper addresses the effect of thermal aging on material internal state that controls both the creep deformation and oxidation behaviour of Type 316H stainless steels when they are exposed at a simulated AGR environment. Experimental results from creep tests are discussed with respect to a multi-scale self-consistent model, while experimental results from oxidation tests are considered with respect to the application of measured short term data to predict the long term oxidation behaviour. Finally, the interaction between oxidation and creep and its impact on high temperature structural integrity of AGR nuclear systems are discussed.
机译：英国在操作高温民用核电系统（称为先进气冷堆（AGR））方面具有独特的经验。延长AGR电站使用寿命的主要挑战之一是了解AGR CO2环境与蠕变疲劳开裂行为之间的相互作用。这是反应堆压力容器内钢部件的寿命限制退化机理之一。本文探讨了热时效对材料内部状态的影响，这种影响控制着316H型不锈钢在模拟AGR环境下暴露时的蠕变变形和氧化行为。针对多尺度自洽模型讨论了蠕变测试的实验结果，同时考虑了将氧化测试的实验结果用于测量短期数据以预测长期氧化行为的实验结果。最后，讨论了氧化和蠕变之间的相互作用及其对AGR核系统高温结构完整性的影响。

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