一级设备的应力与应变分析研究
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摘要
一级设备在核设备中非常重要,在该设备的设计和调试的过程中需要对其进行应力与应变分析,从而确保其安全性。对一级设备的应力与应变分析有两种方法,理论方法和实验方法。通过理论方法,可以得到一级设备在各种工况下的应力与应变状况,从而为设备的设计提供依据;通过实验方法,可以验证理论方法的准确性,并为设备的安全评定提供依据。中国实验快堆(CEFR)主容器属于一级设备,本文结合CEFR主容器的应力与应变分析研究,根据AMSE规范,描述了核安全一级设备的应力与应变分析的理论方法,同时也介绍了测量核安全一级设备的应力与应变的实验方法。
The class 1 equipment is very important in the nuclear device,in the design and testing process required to carry out their stress and strain analysis,so as to ensure their safety.There are two ways to get stress and strain analysis of the class 1 equipment,the theoretical and experimental methods.Through theoretical method can get the stress and strain of the class 1 equipment,so as to provide a basis for the design of the equipment;through the experimental method to verify the accuracy of the theoretical methods and provide a basis for the safety assessment of the equipment.The main ressel of CEFR(China Experimental Fast Reactor) is the class 1 equipment.In this paper,according to the stress and strain analysis research of CEFR main vessel,the theories and expperimental methods of nuclear class 1 equipments stress and strain analysis has been described.
引文
[1]美国机械工程师学会.锅炉及压力容器规范Ⅲ[S].1995.
    [2]国家地震局.核电厂抗震设计规范GB 50267—95[S].北京:中国计划出版社,1998.
    [3]余华金.CEFR堆容器温度场和热应力计算分析[R],2002.
    [4]张如一,等.《应变电测与传感器》[M].北京:清华大学出版社,1999.

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