Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)

Korean Society of Pressure Vessels and Piping (한국압력기기공학회)
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Seismic Performance Evaluation Methodology for Nuclear Power Plants

원전 구조물의 내진성능 평가 방법론 고찰

  • 안호준 (고려대학교 건축사회환경공학부) ;
  • 김유석 (홍익대학교 건축공학부) ;
  • 공정식 (고려대학교 건축사회환경공학부) ;
  • 최영진 (고려대학교 건축사회환경공학부) ;
  • 최세운 (대구카톨릭대학교 건축공학과) ;
  • 이민석 (대한전기협회)
  • Received : 2018.10.31
  • Accepted : 2018.11.14
  • Published : 2018.12.30
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Abstract

Since 2000, the frequency of earthquakes beyond the 5.0 magnitude quake has been increasing in the Korean peninsula. For instance, the 5.0-magnitude earthquake in Baekryong-do in 2003 has occurred, and recent earthquake with Gyeongju(2016) and Pohang(2017) measured respectively magnitude of 5.2 and 5.8 on the Richter scale. As results, the public concern and anxiety about earthquakes are increasing, and therefore it is necessarily required for social infrastructure to reinforce seismic design and energy production facilities directly related to the national economy and security. This study represents the analysis of seismic performance evaluation methodology such as Seismic Margin Assessment (SMA), Seismic Probabilistic Risk Assessment (SPRA), High Confidence Low Probability Failure (HCLPF) in nuclear power plants in order to develop optimal seismic performance improvement. Current methodologies to evaluate nuclear power plants are also addressed. Through review of the nuclear structure evaluation past and current trend, it contributes to be the basis for the improvement of evaluation techniques on the next generation of nuclear power plants.

Keywords

HGHRB5_2018_v14n2_32_f0001.png 이미지

Fig. 1 SPRA Procedure(11)

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Fig. 2 Example of Seismic Fragility Curves(9)

Table 1 SPRA and SMA Methodologies

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Table 2 Seismic Fragility Analysis

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