Nuclear power plants in Korea were designed and evaluated based on the NRC's Regulatory Guide 1.60, a design response spectrum for nuclear power plants. However, it can be seen that the seismic motion characteristics are different when analyzing the Gyeongju earthquake and the Pohang earthquake that has recently occurred in Korea. Compared to the design response spectrum, seismic motion characteristics in Korea have a larger spectral acceleration in the high-frequency region. Therefore, in the case of equipment with a high natural frequency installed in a nuclear power plant, seismic performance may be reduced by reflecting the characteristics of domestic seismic motions. The failure modes of the equipment are typically structural failure and functional failure, with an anchorage failure being a representative type of structural failure. In this study, comparative analyses were performed to decide whether to consider the inelastic behavior of the anchorage or not. As a result, it was confirmed that the seismic performance of the anchorages could be increased by considering the inelastic behavior of an anchorage.

A B S T R A C T
1. 서 론
2. 정착부의 비탄성에너지 흡수계수
3. 캐비닛의 내진성능
    3.1 대상 기기 및 입력지진
    3.2 캐비닛의 지진취약도 곡선
    3.3 비탄성에너지 흡수계수에 대한 논의
4. 결 론
REFERENCES

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• 곽신영(한밭대학교 건설환경공학과) | Kwag Shinyoung (Department of Civil & Environmental Engineering, Hanbat National University) Corresponding author
• 최인길(한국원자력연구원 첨단구조·지진안전연구부) | Choi In-Kil (Advanced Structures and Seismic Safety Research Division, Korea Atomic Energy Research Institute)
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