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概述了根据调研确定的300MW核电站反应堆压力容器密封性能综合研究的总体构思,给出了密封分析程序系统的建立与试验校核的主要研究结果,叙述了密封元件的研制和测试以及热态密封试验与热分析。据此,论述了秦山电站核容器的密封性能,提出了容器类型和密封判据等分类概念,说明了两个观点,即密封变形分析应作为容器总体应力分析的基础及瞬 态密封分析中,热-接触耦合的要点在于确立螺栓温度滞后产生的螺栓载荷热增量,阐述了对密封机理的认识,最后对水压试验的热当量等作了讨论。
The general idea of the comprehensive research on the sealing performance of reactor pressure vessel of 300MW nuclear power plant based on the survey is summarized. The main research results of the establishment and testing of the seal analysis program system are given. The development and testing of the sealing element and the thermal sealing test With thermal analysis. Based on this, the sealing performance of nuclear reactor in Qinshan Power Station is discussed, and the classification concepts of container type and sealing criterion are put forward. Two concepts are described, that is, the analysis of seal deformation should be used as the basis of overall stress analysis and transient seal analysis. The key point of heat-contact coupling is to establish the thermal increment of bolt load caused by the hysteresis of the bolt temperature. The recognition of the sealing mechanism is expounded. Finally, the thermal equivalence of the hydrostatic test is discussed.