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Structural Analysis and Evaluation on the Containment Structure of the Pressurized Water Reactor Plants with Consideration of the Aging Effects

机译:考虑老化效应的压水堆厂房围护结构的结构分析与评价

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The containment structure of a nuclear power plant (NPP) with pressurized water reactor (PWR) is very critical and the last physical barrier and it is irreplaceable equipment, such that the containment design service life is directly related to the nuclear power plant life. Earlier, the 1000MW PWR nuclear power plants were all designed with the design life period of 40-year considered in China, but now the 60-year requirement of the service age of a plant is put forward in order to improve the operation period of nuclear power plant. Therefore, a comprehensive analysis of the impact on the containment structure durability of several factors is conducted and the main influence factors are extracted as follows: the long term effect of the material properties; loads change caused by design aging change; comprehensive durability evaluation on structure materials. Firstly, the design basis for a 60-year design life should be determined according to the requirement. Then, re-evaluate loads and strengths of the materials etc. to ensure its applicability and adjustment method if needed. At the same time, because of the increase of the design service life, the analysis of the parameters closely related to time factor, such as shrinkage, creep, size of the prestressed force loss effect based on the design life of 60 years should be performed. Finally, the technical requirements for structural durability to meet 60-year old are explored and proposed in this paper. As an example, a PWR containment in China is introduced and evaluated based on the 60-year service age, and the evaluation methodology, steps and results are released in this paper. It could be a very good reference, and could also be applied to other assessments on service life extending of the civil structures of nuclear facilities.
机译:具有压水堆(PWR)的核电站(NPP)的安全壳结构非常关键,并且是最后的物理屏障,并且是不可替代的设备,因此安全壳设计使用寿命与核电站的寿命直接相关。此前,在中国考虑的1000MW压水堆核电厂的设计寿命均为40年,但现在提出了60年的电厂使用寿命要求,以延长核电站的运行时间。发电厂。因此,对几个因素对安全壳结构耐久性的影响进行了综合分析,主要影响因素提取如下:材料性能的长期影响;设计老化引起的载荷变化;对结构材料进行全面的耐久性评估。首先,应根据要求确定60年设计寿命的设计依据。然后,重新评估材料等的负载和强度,以确保其适用性和调整方法(如果需要)。同时,由于设计寿命的增加,应基于60年的设计寿命对与时间因素密切相关的参数进行分析,如收缩率,蠕变,预应力损失效果的大小。 。最后,探讨并提出了满足60年历史的结构耐久性的技术要求。例如,根据中国60年的服役年限,介绍并评估了压水堆的安全壳,并发布了评估方法,步骤和结果。它可能是一个很好的参考,也可以用于其他有关延长核设施民用结构使用寿命的评估。

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