Evaluation of Clearance to Stop Requirements in A Seismically Isolated Nuclear Power Plant

被引:6
|
作者
An, Gyeonghee [1 ]
Kim, Minkyu [1 ]
Jung, Jae-Wook [1 ]
Mosqueda, Gilberto [2 ]
Marquez, Joaquin Fabian [2 ]
机构
[1] Korea Atom Energy Res Inst, Daejeon 34057, South Korea
[2] Univ Calif San Diego, Dept Struct Engn, San Diego, CA 92093 USA
基金
新加坡国家研究基金会;
关键词
lead rubber bearing (LRB); seismic isolation; nuclear power plant (NPP); performance criteria; clearance to the stop (CS); ultimate property diagram (UPD); DYNAMIC STABILITY; BEARINGS;
D O I
10.3390/en13226156
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
Seismically isolated nuclear power plants (NPPs) can provide substantial benefits towards reducing the failure probability of NPPs, especially for beyond design basis earthquake shaking. One risk posed by seismic isolation is the potential for pounding to a stop or moat wall, with currently little guidance provided by design standards on how to address this concern. In this paper, a structural model of an isolated NPP based on the Advanced Power Reactor 1400 MW is enveloped with moat walls and advanced bearing models. The bearing models account for large strain behavior through failure based on full-scale experiments with lead rubber bearings (LRBs). Using these analytical models and a measured ultimate property diagram from LRB failure tests, the range of clearance to the stop considering the performance criteria for the NPP is investigated. Although the analysis results are dependent on the particular models, ground motions, and criteria employed, this research provides an overview of the seismic response and performance criteria of an isolated NPP considering the clearance to the stop.
引用
收藏
页数:19
相关论文
共 50 条
  • [21] Application of PSA Technology in Technical Requirements Optimization of Nuclear Power Plant
    Yu, Xipeng
    Yang, Zhi
    2022 4TH INTERNATIONAL CONFERENCE ON SYSTEM RELIABILITY AND SAFETY ENGINEERING, SRSE, 2022, : 133 - 138
  • [22] Technical requirements for the ASME PRA standard for nuclear power plant applications
    Fleming, KN
    Bernsen, SA
    Simard, RL
    PSAM 5: PROBABILISTIC SAFETY ASSESSMENT AND MANAGEMENT, VOLS 1-4, 2000, (34): : 2795 - 2800
  • [23] A REGULATORY HISTORY OF EDUCATIONAL REQUIREMENTS FOR NUCLEAR-POWER PLANT STAFF
    PERSENSKY, JJ
    GOODMAN, C
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1985, 50 (NOV): : 64 - 64
  • [24] Transmission Lines Main and Backup Fault Clearance - Impact on A Nuclear Power Plant
    Kiran, T. Chandra
    Theivarajan, N.
    PROCEEDINGS OF THE 2014 IEEE 2ND INTERNATIONAL CONFERENCE ON ELECTRICAL ENERGY SYSTEMS (ICEES), 2014, : 20 - 25
  • [25] A comparative evaluation of design provisions for seismically isolated buildings
    Yenidogan, Cem
    Erdik, Mustafa
    SOIL DYNAMICS AND EARTHQUAKE ENGINEERING, 2016, 90 : 265 - 286
  • [26] An evaluation of computerized procedure system in nuclear power plant
    Min, DW
    Chung, YH
    Kim, B
    ANALYSIS, DESIGN AND EVALUATION OF HUMAN-MACHINE SYSTEMS 2001, 2002, : 519 - 524
  • [27] Service Life Evaluation of Nuclear Power Plant Cable
    Tian, Feng
    Ni, Yan-rong
    Su, Wen
    RENEWABLE AND SUSTAINABLE ENERGY II, PTS 1-4, 2012, 512-515 : 890 - +
  • [28] EVALUATION OF THE THERMAL EFFECTS OF A NUCLEAR POWER PLANT.
    Ioannilli, E.
    Smedile, E.
    1975, : 83 - 94
  • [29] ENVIRONMENTAL FATIGUE EVALUATION OF A KOREAN NUCLEAR POWER PLANT
    Oh, Chang-Kyun
    Kim, Hyun-Su
    Youm, Hag-Ki
    Jin, Tae-Eun
    Kim, Young-Jin
    ICONE 16: PROCEEDING OF THE 16TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2008, VOL 4, 2008, : 113 - 119
  • [30] INVESTIGATION AND EVALUATION OF EARTHQUAKES IN NUCLEAR POWER PLANT SITING
    Tian ShengqingBeijing Institute of Nuclear Engineering Beijing
    地震地质, 1993, (04) : 296 - 305+295