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首页> 外文会议>ASME Pressure Vessels amp;amp;amp; Piping Conference >RECENT DEVELOPMENTS IN THE R5 PROCEDURES FOR ASSESSING THE HIGH TEMPERATURE RESPONSE OF STRUCTURES
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RECENT DEVELOPMENTS IN THE R5 PROCEDURES FOR ASSESSING THE HIGH TEMPERATURE RESPONSE OF STRUCTURES

机译：R5近期发展的近期发展，用于评估结构的高温响应

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The R5 procedures have been developed within the UK power generation industry to assess the integrity of nuclear and conventional plant operating at high temperatures. Within R5, there are specific procedures for assessing creep-fatigue crack initiation in initially defect-free components (Volume 2/3), components containing defects (Volume 4/5), dissimilar metal weldments (Volume 6) and similar metal ferritic weldments under steady loading (Volume 7). A key driver for continued developments in the R5 Procedure is the operational feedback from thirty years of operation of the UK Advanced Gas-Cooled Reactor (AGR) fleet. This experience from operation of the UK AGR fleet can be used to inform the design and operation of future high temperature reactors. Some of the lessons learnt from long-term operation of austenitic stainless steels at high temperatures are detailed briefly within this paper. Further, this paper briefly outlines the current R5 procedures and then focuses on two significant recent developments in these procedures: treatment of carburisation and its impact on creep-fatigue crack initiation and improved methods for predicting creep-fatigue crack growth under combined primary and secondary loads.
机译：R5程序已在英国发电业内开发，以评估在高温下运行的核和常规工厂的完整性。在R5内，有具体方法用于评估初始缺陷的组分（体积2/3），含有缺陷的组分（体积4/5），不同金属焊接（体积6）和类似的金属铁素体焊接中的蠕变 - 疲劳裂纹引发稳定装载（第7卷）。 R5持续发展的关键驱动程序是英国先进的气冷反应堆（AGR）舰队三十年的运作的运行反馈。这种来自英国农业队列的经验可用于通知未来高温反应堆的设计和运行。在本文中简要介绍，从高温下从奥氏体不锈钢长期运行中学到的一些经验教训。此外，本文简要概述了目前的R5程序，然后侧重于这些程序中的两个重要发展：碳擦除处理及其对蠕变 - 疲劳裂纹引发的影响及预测初级和二次负载下的蠕变疲劳裂纹生长的改进方法。

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