核电厂安全壳隔震减振分析

英文篇名：Analysis of Structural Seismic Response of Nuclear Power Plant Concrete Containment Vessel with Isolating Devices
中文刊名：核动力工程
英文刊名：Nuclear Power Engineering
作者：侯钢领 ; 陈树华 ; 李冬梅
英文作者：HOU Gang-ling1 ; CHEN Shu-hua1 ; LI Dong-mei2 (1.College of Aerospace and Civil Engineering ; Harbin Engineering University ; Harbin ; 150001 ; China ; 2.China National Petroleum Offshore Engineering CO.LTD ; Beijing ; 100007 ; China)
中文关键词：核电厂 ; 安全壳 ; 隔震技术 ; 抗震性能 ; 隔震设计
英文关键词：Nuclear power plant ; Concrete Containment Vessel ; Isolating technology ; Seismic capacity ; Isolating design
出版日期：2011-06-30
机构：哈尔滨工程大学航天与建筑工程学院;中国石油集团海洋工程有限公司;
年：2011
期：S1
出版单位：核动力工程

摘要

为有效减小地震灾害对核电厂安全壳的影响,基于安全壳的动力特性,从隔震技术原理出发,分析安全壳采用隔震技术的可行性。以某核电厂为对象,对比分析了隔震技术对安全壳的减震效果,并应用优化技术进行了隔震设计。结果表明,采用隔震技术可显著提高安全壳的抗震性能。
In order to reduce the effect of seismic disaster on the nuclear power plant reinforced Concrete Containment Vessel(CCV),the feasibility of the application of isolating technology in CCV is analyzed based on the CCV dynamic response characteristics and the principle of the structural isolating devices technology.Taking a nuclear power station as an example,the seismic responses of normal CCV with isolating CCV is compared and analyzed,and isolating design is conducted by optimized technology.The results show that the the isolating CCV can greatly improve anti-seismic capacity.

引文

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