포항지진에 대한 원자력발전소 구조물 및 기기의 지진응답 분석

서지정보

ㆍ발행기관 : 한국지진공학회 ㆍ수록지정보 : Jorunal of the Earthquake Engineering Society of Korea / 22권 / 3호
ㆍ저자명 : 임승현, 최인길

목차

A B S T R A C T
1. 서 론
2. 지진응답해석을 위한 입력지진
2.1 포항지진의 특징
2.2 원자력발전소 설계응답스펙트럼에 부합하는 인공지진 생성
3. 원자력발전소의 층응답스펙트럼
3.1 격납건물의 층응답스펙트럼
3.2 보조건물의 층응답스펙트럼
4. 원자력발전소 전기기기의 내진성능
4.1 CPC/CEAC 캐비닛의 내진성능 비교
4.2 MCC 캐비닛의 내진성능 비교
5. 결 론
REFERENCES

영어 초록

The probabilistic seismic safety assessment is one of the methodology to evaluate the seismic safety of the nuclear power plants. The site characteristics of the nuclear power plant should be reflected when evaluating the seismic safety of the nuclear power plant. The Korea seismic characteristics are strong in high frequency region and may be different from NRC Regulatory Guide 1.60, which is the design spectrum of nuclear power plants. In this study, seismic response of a nuclear power plant structure by Pohang earthquake (2017.11.15. (KST)) is investigated. The Pohang earthquake measured at the Cheongsong seismic observation station (CHS) is scaled to the peak ground acceleration (PGA) of 0.2 g and the seismic acceleration time history curve corresponding to the design spectrum is created. A nuclear power plant of the containment building and the auxiliary buildings are modeled using OPENSEES to analyze the seismic response of the Pohang earthquake. The seismic behavior of the nuclear power plant due to the Pohang earthquake is investigated. And the seismic performances of the equipment of a nuclear power plant are evaluated by the HCLPF. As a result, the seismic safety evaluation of nuclear power plants should be evaluated based on site-specific characteristics of nuclear power plants.

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