Current state of in-cabinet response spectra for seismic qualification of equipment in nuclear power plants

被引:15
|
作者
Gupta, Abhinav [1 ]
Cho, Sung-Gook [2 ]
Hong, Kee-Jeung [3 ]
Han, Minsoo [2 ]
机构
[1] NC State Univ, Dept Civil Construct & Environm Engn, Raleigh, NC 27695 USA
[2] Innose Tech Co Ltd, R&D Ctr, Incheon, South Korea
[3] Kookmin Univ, Sch Civil & Environm Engn, Seoul, South Korea
关键词
RITZ VECTOR APPROACH;
D O I
10.1016/j.nucengdes.2018.12.017
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Many nuclear power plants in the south eastern region of South Korea are undertaking seismic qualification studies due to the recent earthquake in Gyeongju region. The records from this earthquake contain high frequency content compared to the frequency exhibited in most of the design basis Safe Shutdown Earthquakes used in the design of nuclear power plants. While the high frequency ground motions are not detrimental to the structures due to relatively smaller displacements, such motions can lead to functionality related failures in electrical equipment and systems such as control relays. The seismic qualification of relays and other such instruments require characterization of in-cabinet response spectra (ICRS) in the cabinet or control panels where they are mounted. The current practice of generating ICRS, in many cases, uses constant amplification factors which are based on studies containing low frequency ground motions. Cabinets can often have higher frequency modes which can amplify the motion if it contains high frequency pulses. Finite element analysis to evaluate the dynamic characteristics of cabinet is highly impractical because each cabinet is vastly different from other cabinets and a given plant contains hundreds of such cabinets and control panels. Therefore, a method is needed to evaluate accurate dynamic characteristics of cabinets and control panels in a relatively simple manner. This paper presents the details of such a method called Ritz vector approach and also compares the ICRS of an actual cabinet for a high frequency input motion with that for a low frequency input motion.
引用
收藏
页码:269 / 275
页数:7
相关论文
共 50 条
  • [21] Evaluating adaptive vertical seismic isolation for equipment in nuclear power plants
    Najafijozani, Mohammadreza
    Becker, Tracy C.
    Konstantinidis, Dimitrios
    NUCLEAR ENGINEERING AND DESIGN, 2020, 358
  • [22] Qualification Test Standards Research of Electrical Equipment Important to Safety of Nuclear Power Plants
    Guo, Yin-Hui
    Wang, Zhong-Qiu
    Zhang, Yun-Bo
    Feng, Yan
    Qiao, Ning
    Liu, Jing-bin
    NUCLEAR POWER PLANTS: INNOVATIVE TECHNOLOGIES FOR INSTRUMENTATION AND CONTROL SYSTEMS, 2017, 400 : 153 - 161
  • [23] ENVIRONMENTAL QUALIFICATION OF ESSENTIAL SAFETY-RELATED EQUIPMENT FOR NUCLEAR-POWER PLANTS
    MCNEILL, H
    NUCLEAR SAFETY, 1983, 24 (05): : 658 - 670
  • [24] CURRENT CONSIDERATIONS IN SEISMIC DESIGN OF NUCLEAR-POWER STATION EQUIPMENT
    SMALL, RJ
    IEEE TRANSACTIONS ON POWER APPARATUS AND SYSTEMS, 1972, 91 (05): : 1863 - &
  • [25] RESPONSE OF EQUIPMENT IN NUCLEAR-POWER PLANTS TO AIRPLANE CRASH
    SCHALK, M
    WOLFEL, H
    NUCLEAR ENGINEERING AND DESIGN, 1976, 38 (03) : 567 - 582
  • [26] Analysis on the construction methods of seismic design spectra for nuclear power plants
    Xu, Longjun
    Li, Shuang
    Xie, Lili
    Tumu Gongcheng Xuebao/China Civil Engineering Journal, 2012, 45 (SUPPL.1): : 1 - 8
  • [27] Seismic demand estimation of electrical cabinet in nuclear power plant considering equipment-anchor-interaction
    Cho, Sung Gook
    Salman, Kashif
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2022, 54 (04) : 1382 - 1393
  • [28] Procedure and Method of Equipment Qualification for Solenoid-Operated Valves Used in Nuclear Power Plants
    Lim, Byung-Ju
    Park, Chang-Dae
    Chung, Kyung-Yul
    TRANSACTIONS OF THE KOREAN SOCIETY OF MECHANICAL ENGINEERS A, 2011, 35 (06) : 683 - 691
  • [29] POWER RESPONSE SPECTRUM TRANSFORMATIONS IN EQUIPMENT QUALIFICATION
    UNRUH, JF
    KANA, DD
    MECHANICAL ENGINEERING, 1984, 106 (08) : 88 - 88
  • [30] POWER RESPONSE SPECTRUM TRANSFORMATIONS IN EQUIPMENT QUALIFICATION
    UNRUH, JF
    KANA, DD
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 1985, 107 (02): : 197 - 202