| 反应堆压力容器60a设计寿命研究中力学性能分析 |
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| 引用本文： | 杜娟,孙英学,卢岳川. 反应堆压力容器60a设计寿命研究中力学性能分析[J]. 原子能科学技术, 2008, 42(Z2) |
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| 作者姓名： | 杜娟 孙英学 卢岳川 |
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| 作者单位： | 中国核动力研究设计院,核反应堆系统设计技术国家级重点实验室,四川,成都,610041 |
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| 摘 要： | 本文以百万千瓦级核电站(CNP1000)反应堆压力容器为例,分析研究了设计瞬态和疲劳损伤、脆性破坏等因素对60 a设计寿命反应堆压力容器的影响.针对不同的分析内容,选择反应堆压力容器具有代表性的部位,论证了60 a寿期末反应堆压力容器结构的完整性.
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| 关 键 词： | 反应堆压力容器 60a设计寿命 力学性能 |
Mechanical Behavior Analysis in Study of 60a Design Life for Reactor Pressure Vessel |
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| DU Juan,SUN Ying-xue,LU Yue-chuan. Mechanical Behavior Analysis in Study of 60a Design Life for Reactor Pressure Vessel[J]. Atomic Energy Science and Technology, 2008, 42(Z2) |
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| Authors: | DU Juan SUN Ying-xue LU Yue-chuan |
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| Affiliation: | DU Juan,SUN Ying-xue,LU Yue-chuan (State Key Laboratory of Reactor System Design Technology,Nuclear Power Institute of China,Chengdu 610041,China) |
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| Abstract: | This paper presents the mechanical behavior analysis in the study of 60 a design life for reactor pressure vessel(RPV),including the fatigue analysis due to 60 a design transients,the analysis of fatigue crack propagating and the analysis of non ductile fatigue risk.By choosing the most representative parts of CNP1000 RPV,the integrity structure of RPV after 60 a design life was demonstrated. |
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| Keywords: | reactor pressure vessel 60 a design life mechanical behavior |
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