首页> 外文会议>ASME Pressure Vessels and Piping conference >DEVELOPMENT OF AN EVALUATION METHOD FOR SEISMIC ISOLATION SYSTEMS OF NUCLEAR POWER FACILITIES (PART 1), THE WORK SCHEDULE OF PROJECT AND A SEISMIC DESIGN OF CROSSOVER PIPING SYSTEM
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DEVELOPMENT OF AN EVALUATION METHOD FOR SEISMIC ISOLATION SYSTEMS OF NUCLEAR POWER FACILITIES (PART 1), THE WORK SCHEDULE OF PROJECT AND A SEISMIC DESIGN OF CROSSOVER PIPING SYSTEM

机译:核动力设施地震隔离系统评估方法(部分1),项目工作时间表和跨接管道系统抗震设计的开发

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This paper provides a part of series of "Development of an Evaluation Method for Seismic Isolation Systems of Nuclear Power Facilities". This part describes the work schedule of this project and the summary of a seismic design for crossover piping system. Since the Southern Hyogo Prefecture Earthquake in 1995, a seismic isolated design has been widely adopted for Japanese typical buildings. The Japanese government accepted utilizing seismic isolation technology for nuclear power facilities with the 2006 revision of the "Regulatory Guide for Reviewing Seismic Design of Nuclear Power Reactor Facilities". Under these backgrounds, the Japan national project with the participation of all electric power companies and reactor vendors has been started from 2008 to develop seismic isolation systems of nuclear power facilities under the support of the Ministry of Economy, Trade and Industry. In the design of seismic isolated plant, the crossover piping systems, such as Main Steam line and other lines related to the safety system have the important roles for overall plant safety. Therefore, the design of multiply supported piping systems between isolated and non-isolated buildings is one of the major key issues. This paper focuses on the seismic response analysis of Main Steam crossover piping between seismic isolated Reactor Building and non-isolated Turbine Building. Multiple input response spectra and time history analyses of the crossover piping have been performed and the structural integrity of piping and the validity of the multiple input analysis method have been verified based on comparisons with the results obtained by conventional response spectrum analysis using enveloped floor response spectrum.
机译:本文提供了“开发核电设施隔震系统评估方法”系列的一部分。本部分描述了该项目的工作时间表以及交叉管道系统的抗震设计摘要。自1995年兵库县南部地震以来,地震隔离设计已被日本典型建筑广泛采用。日本政府于2006年修订了《核动力反应堆设施抗震设计审查规程指南》,从而接受了将地震隔离技术用于核动力设施。在这种背景下,日本国家项目从2008年开始启动,所有电力公司和反应堆供应商都参与其中,以在经济,贸易和工业部的支持下开发核电设施的地震隔离系统。在地震隔离工厂的设计中,交叉管道系统(例如主蒸汽管线和与安全系统相关的其他管线)对于整个工厂的安全起着重要作用。因此,在隔离和非隔离建筑物之间设计多支撑管道系统是主要的关键问题之一。本文着重分析了隔震反应堆厂房和非隔震汽轮机厂房之间主蒸汽交叉管道的地震响应分析。通过与使用包络底板响应谱的常规响应谱分析结果进行比较,验证了交叉管道的多次输入响应谱和时程分析,并验证了管道的结构完整性和多次输入分析方法的有效性。 。

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