Analysis of Seismic Fragility Parameter of Fluid-filled Container

被引：0
|
作者：
Ye X. [1 ]
Zhang Z. [1 ]
Wan L. [1 ]
机构：
[1] Institute of Nuclear and New Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing
来源：
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2019年 / 53卷 / 04期
关键词：
ASG tank; Housner model; Randomness; Seismic fragility;
D O I：
10.7538/yzk.2018.youxian.0440
中图分类号：
学科分类号：
摘要：
The seismic fragility analysis method of the equipment in nuclear power plant and the parameterized seismic fragility analysis model were introduced in this paper. The Housner model was adopted to calculate the dynamical response of a typical fluid-filled container (ASG tank) in nuclear power plant. The median value, variability and uncertainty of each seismic fragility parameter of ASG tank were calculated. The fragility curve was drawn, and the value of high confidence of low probability of failure (HCLPF) was obtained. The results show that the ASG tank has a lower HCLPF value than the safe shutdown earthquake (SSE) level and is the equipment with low seismic resistance. It needs to be structurally strengthened. © 2019, Editorial Dept. of JA. All right reserved.
引用
收藏
页码：711 / 717
页数：6
相关论文
共 9 条
  • [1] Kennedy R.P., Methodology for deriving seis-mic fragilities, TR-103959, (1994)
  • [2] Reed J.W., Kennedy R.P., Buttemer D.R., Et al., A methodology for assessment of nuclear power plant seismic margin, NP-6041-M-Rev.1, (1991)
  • [3] Reed J.W., Kennedy R.P., Methodology for developing seismic fragilities, TR-103959, (1994)
  • [4] Campbell R., Hardy G., Merz K., Seismic fragility application guide, TR-1002988, (2002)
  • [5] Bohn M.P., Lambright J.A., Procedures for the External Event Core Damage Frequency Analyses for NUREG-1150, (1990)
  • [6] Wen J., Lu Y., Xu Y., Et al., Seismic analysis of auxiliary feedwater system tank in nuclear power plant, Atomic Energy Science and Technology, 49, 5, pp. 897-902, (2015)
  • [7] Housner G.W., Dynamic pressures on accelerated fluid containers, Bulletin of the Seismological Society of America, 47, 1, pp. 15-35, (1957)
  • [8] Newmark N.M., Hall W.J., Development of criteria for seismic review of selected nuclear power plants, NUREG/CR-0098, (1978)
  • [9] Kennedy R.P., Campbell R.D., Wesley D.A., Et al., Subsystem response review, NUREG/CR-1706, (1980)
1