【摘要】 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客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定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。更多还原

【Abstract】 The general conception of a special research on sealing behaviour of PWR vessel is described and the major results centering on the establishment of sealing analysis program system and its experimental verification, along with the description on the development and measurement of sealing ring, the thermal sealing test and the relevant analysis are given. On the basis of the above approach, the vessel sealing behaviours of 300 MWe Qinshan Nuclear Power Plant are evaluated. A concept about the classification of pressure vessels and their sealing criteria are proposed. Two viewpoints about the analysis are suggested, which are that the vessel sealing deformation analysis should be regarded as a basis of the general stress analysis and that bolt loading increment caused by the bolt temperature lag should be taken as a key point when considering the thermo-contact coupling in transient sealing analysis. The understandings about the sealing mechanism are expounded and the thermal equivalent of hydrostatic test is discussed.更多还原