대한토목학회논문집 (KSCE Journal of Civil and Environmental Engineering Research)

  • 제26권5A호
  • /
  • Pages.901-908
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  • 2006
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  • 1015-6348(pISSN)
  • /
  • 2799-9629(eISSN)
대한토목학회 (Korean Society of Civil Engeneers)
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국내 부착식 텐던 격납건물(CANDU형)의 구조거동 분석 도구 개발

Development of Analysis Tool for Structural Behavior of Domestic Containment Building with Grouted Tendon (CANDU-type)

  • 이상근 (서울특별시의회 건설전문위원실) ;
  • 송영철 (한전전력연구원 환경구조연구소)
  • 투고 : 2006.03.28
  • 심사 : 2006.05.24
  • 발행 : 2006.09.30
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초록

안전성 관련 구조물인 원자력 격납건물은 시간의 흐름에 따라 콘크리트와 텐던의 물리적 성질 변화로 구조거동의 미세한 변화를 가져오기 때문에 주기적 점검을 통한 구조건전성 검증이 필요하다. 본 연구에서는 국내 부착식 텐던 격납건물인 CANDU형의 월성 원전을 대상으로 미세 구조거동 분석이 가능한 'SAPONC-CANDU' 프로그램을 개발하였으며, 이는 온도와 시간종속성 영향인자들 즉, 크리프, 건조수축, 텐던의 인장력 하에서 격납건물 콘크리트 속에 매립되어 있는 진동식 와이어 변형률 게이지의 변형률 변화량에 대한 예측값을 계산하는 알고리즘에 기초한다. 개발된 프로그램의 구동을 위해서 변형률 게이지의 계측값이 입력데이타로 사용되고 최종적으로 각각의 변형률 게이지에 대해서 변형률 변화량의 예측값, 예측선, 예측폭이 그래프 형태로 제공되기 때문에 국내 원자력발전소 CANDU형 격납건물의 구조건전성을 평가하는 현장 관리자가 이를 손쉽게 활용할 수 있다.

The structural integrity of containment building in Nuclear Power Plants has to be verified by the ISI(In Service Inspection) because there are some variations on the structural behavior of it due to the change of the physical properties of concrete and tendon with the lapse of time. In this study, the program 'SAPONC-CANDU' which can monitor and analyze the structural behavior of the containment building with grouted tendon (CANDU-type, 'Wolsong unit-2, 3, and 4' in Korea) was developed. This program is based on the algorithm which can calculate the prediction values of the quantities of strain variation for the vibrating-wire strain gauges embedded into the concrete of the containment building under temperature and time dependent factors which are creep, shrinkage, and prestressing force. The readings of the strain gauges are used as input data for the operation of the program. And it finally provides graphically a prediction value, line and band of the quantity of strain variation for the respective strain gauges, therefore, it is thought that the site engineers are able to assess the structural integrity of the domestic containment building with grouted tendon with easy using this program.

키워드

참고문헌

  1. U.S. Nuclear Regulatory Commission (1990) Inservice inspection of ungrouted tendons in prestressed concrete containment structures. Regulatory Guide 1.35 Rev. 3
  2. Canadian Standards Association (1984) In-Service Examination and Testing Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants. CSA N287.7-M80
  3. Canadian Standards Association (1984) Pre-operational Proof and Leakage Rate Testing Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants. CSA N287.6-M80
  4. France EDF (1980) Strength and leak tightness testing of the prestressed concrete containment with a leaktight liner. RCC-G Part III
  5. American Society of Mechnical Engineers (1989) Structural Integrity Test of Concrete Containment Structures. ASME Boiler and Pressure Vessel Code, Sec. III, Div 2, Article CC-6000
  6. CANATOM (1995) Integrity surveillance of the prestressing system by strain gauges for the containment structure of the reactor building. Wolsong-2,3,4 NPP Technical Specification 8600-21206-0008-00- TS-A, Rev. 0
  7. CANATOM (1996) Integrity surveillance of the prestressing system by strain gauges for the containment structure of the reactor building. wolsong-2,3,4 NPP Technical Specification 8600-21206-0008-00- TS-A, Rev. 2
  8. CANATOM (1995) Reactor building containment prediction of upper and lower limits of strain gauge readings during the pressure test. Wolsong-2,3,4 NPP Design Report 8600-21020-0002-00-DR-A, Rev. 0
  9. DIN-4227 (1973, 1988) Concrete, Reinforced and Prestressed Concrete Structures - Part 1: Design
  10. CANATOM (1994) Reactor building containment sturcture stress analysis. Wolsong-2 NPP Design Report 8602-21020-0002-00-DR-A, Rev. 1
  11. CANATOM (1994) Reactor building containment sturcture openings and backfill pressure stress analysis, Wolsong-3,4 NPP Design Report 8634-21020-0004-00-DR-A, Rev. 1