포항지진에 대한 원자력발전소 구조물 및 기기의 지진응답 분석

다국어 초록 (Multilingual Abstract)

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.

목차 (Table of Contents)

• 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

참고문헌 (Reference)

1 최인길, "설계초과 지진에 대한 원전 지진안전성 평가기술 고찰 및 제언" 한국압력기기공학회 13 (13): 1-15, 2017

2 Choi IK, "Transactions of the Korean Nuclear Society Spring Meeting" 2017

3 "The U.S. Geological Survey"

4 Bommer JJ, "The Effective Duration of Earthquake Strong Motion" 3 (3): 127-172, 1999

5 Sursock J, "Seismic Probabilistic Risk Assessment Implementation Guide" EPRI 2013

6 ASCE, "Seismic Analysis of Safety-Related Nuclear Structures and Commentary. ASCE Standard 4-98"

7 US Nuclear Regulatory Commission, "Regulatory Guide 1.60: Design Response Spectra for Seismic Design of Nuclear Power Plants"

8 XU JIM, "Probabilistic Computer Analysis for Rapid Evaluation of Structures" Oak Ridge National Laboratory (ORNL) 2007

9 Reed JW, "Methodology for Developing Seismic Fragilities" EPRI 1994

10 Korea Meteorological Administration, "Earthquake notification - 2017. 11.15. Official notice"

11 "Central Disaster Safety Measures Headquarters, Press Releases: Recovery cost of Pohang earthquake"

12 이철호, "2016년 9월 12일 M5.8 경주지진의 데미지 포텐셜 분석 및 내진공학 측면의 시사점" 한국지진공학회 20 (20): 527-536, 2016