首页> 外文会议>International conference on structural mechanics in reactor technology;SMiRT 17 >PRELIMINARY SEISMIC FRAGILITY ANALYSIS OF SELECTED HEAVYCOMPONENTS IN LNNP UNIT 1 REACTOR BUILDING
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PRELIMINARY SEISMIC FRAGILITY ANALYSIS OF SELECTED HEAVYCOMPONENTS IN LNNP UNIT 1 REACTOR BUILDING

机译:LNNP 1号反应堆厂房中选定重组分的初步地震易损性分析

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The paper studies the fragility of heavy components in Leningrad Nuclear Power Plant unit 1 reactor building. Theanalyzed components are: (1) drum separators (4 pcs); (2) main coolant pumps (8 pcs); (3) suction headers (2 pcs); (4)pressure headers (2 pcs); (5) refuelling machine (1 pcs). The reactor stack was excluded from the analysis based on thestudy of structural drawings of reactor stack and supporting metal structures. It was judged that the multitude (1693 pcs)of channels in reactor core and adjacent small bore piping ( 50 mm and 70 mm) forms a structure, which inherently hasseismic capacity and damping. The fragility of a component is defined as the conditional probability of its failure givena value of the response parameter, such as stress, moment, and spectral acceleration, peak ground acceleration [1].Using the lognormal-distribution assumption, the fragility (I.e., the probability of failure, f') at any nonexceedenceprobability level Q can be derived as f'=Φ[(ln(a/(_A) +βUΦ-1 (Q))/βR] where Q = P(f < f'|a) is the probability that the conditional probability f is less than f' for a peak ground acceleration a.(_A) is the median ground acceleration capacity, βR is the logarithmic standard deviation representing the inherentrandomness about A, and βU is the logarithmic standard deviation representing the uncertainty in the median value. Thequantity Φ(.) is the standard Gaussian cumulative distribution function, and Φ-1(.) is its inverse. The stress resultantresponses for the investigated heavy component supports are evaluated for drum separator, main coolant pump, suctionheader, pressure header, and refueling machine. For the purpose of defining fragility curves, the possible failure modesmust be identified and evaluated. The results of the fragility analysis are the parameters A, βU, βR for selected heavycomponents.
机译:本文研究了列宁格勒核电站1号反应堆厂房中重​​组分的脆性。分析的组件为:(1)鼓式分离器(4个); (2)主冷却液泵(8个); (3)吸头(2个); (4)压力头(2个); (5)加油机(1台)。根据堆堆结构图和支撑金属结构的研究,将堆堆从分析中排除。判断反应堆堆芯和相邻的小口径管道(50 mm和70 mm)中的多个通道(1693个)形成了固有的抗震能力和阻尼结构。组件的脆弱性定义为在给定响应参数值(例如应力,力矩和频谱加速度,峰值地面加速度)的情况下其失效的条件概率。使用对数正态分布假设,脆弱性(即可以将任何不超过概率水平Q的故障概率f')推导为f'=Φ[(ln(a /(_ A)+βUΦ-1(Q))/βR]其中Q = P(f

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