Assessment of the Internal Pressure Fragility of the CANDU Type Containment Buildings using Nonlinear Finite Element Analysis

비선형 유한요소해석을 이용한 CANDU형 격납건물의 내압취약도 평가

  • Received : 2010.07.13
  • Accepted : 2010.07.23
  • Published : 2010.08.31

Abstract

In this paper an assessment of the internal pressure fragility of the CANDU type containment buildings is performed. The uncertainties of the performance of the containment buildings, material properties and tendon characteristics are referred from the in-service reports of Wolsung Unit 1. The containment buildings are modeled as a three-dimensional finite elements with considering the major opening and penetrations. A new method to evaluate the probabilistic fragility of the massive structural system is developed. The fragility curves of the target containment building are presented with repect to the failure modes and reliability levels. The center of wall is reveled as the most weak structural component of the containment building in the sense of the rupture and catastrophic rupture failure modes.

CANDU형 격납건물에 대하여 극한내압하중에 대한 확률론적 취약도 평가를 수행하였다. 격납건물 성능의 불확실성은 가동중 검사 결과를 통해 얻어진 재료 물성치 중앙값과 텐던 긴장력 중앙값을 적용하여 고려하였다. 격납건물은 개구부를 고려하여 3차원 유한요소로 모델링하였으며, 확률론적 취약도 평가를 위하여 대규모의 비선형 유한요소해석 모델을 적용하기에 적합한 효율적인 취약도 평가기법을 개발하였다. 월성 1호기 격납건물에 대한 물성치를 사용하였다. 개발된 새로운 취약도 평가기법을 도입하여 각각의 파괴모드에 대한 취약도 평가를 수행하였으며, 파괴모드 별, 신뢰도 수준별 취약도 곡선을 도출하였다. 벽체 중단부가 극한내압발생으로 인한 방사능물질 누출에 가장 취약한 것으로 나타났다.

Keywords

References

  1. 김선훈 (2010) 원자로 격납건물의 3차원 구조해석 시스템, 한국전산구조공학회 논문집, 23(2), pp.235-243.
  2. 문일환, 안성문, 김태영 (2009) 원자로건물의 확률론적 극한 내압 평가, 대한토목학회 정기학술대회.
  3. 이홍표, 전영선 (2006) 철근콘크리트 격납건물의 비선형 해석을 위한 쉘 유한요소, 한국전산구조공학회 논문집, 19(1), pp.93-103.
  4. 이홍표, 전영선, 이상진 (2007) 한국형 원전 격납건물의 비선형 해석에 관한 연구, 한국전산구조공학회 논문집, 20(3), pp.353-364.
  5. 한국수력원자력(주) 월성원자력본부 (2008) 월성원자력 1호기 25년차 원자로건물 포스트텐셔닝계통 가동중검사 최종 보고서.
  6. AECL (2007) Assessment of the Pressure Capacity of Containment Penetrations and Airlock Seals. Rev. 0, 66RF-03612-ASD-002, Atomic Energy of Canada Limited, May.
  7. Belarbi, A., Hsu T.T.C. (1994) Constitutive Laws of Concrete in Tension and Reinforcing Bars Stiffened by Concrete, ACI Structural Journal, 91(4), pp.465-473.
  8. CANATOM (1995) Reactor Building Containment Structure Ultimate Pressure Capacity, Design Report.
  9. Clauss, D.B., Horschel, D.S., Blejwas, T.E. (1987) Insights into the Behavior of LWR Steel Containment Buildings During Severe Accidents. Nuclear Engineering and Design, 100, pp.189-204. https://doi.org/10.1016/0029-5493(87)90042-2
  10. Dameron, R.A., Zhang, L., Rashid, Y.R., Vargas, M.S. (2000) Pretest Analysis of a 1:4-Scale Prestressed Concrete Containment Vessel Model, NUREG/CR-6685, SAND2000-2093, ANATECH Corporation, San Diego, CA and Sandia National Laboratories, Albuquerque, NM, October.
  11. Hessheimer, M.F., Klamerus, E.W., Rightley, G.S., Lambert, L.D., Dameron, R.A. (2003) Overpressurization Test of a 1:4-Scale Prestressed Concrete Containment Vessel Model. NUREG/ CR-6810, Sandia National Laboratories, Albuquerque NM. March.
  12. Khoury, G.A. (1992) Compressive Strength of Concrete at High Temperatures: a Reassessment, Magazine of Concrete Research, 44(161), pp.291-309. https://doi.org/10.1680/macr.1992.44.161.291
  13. Kulak, R.F., Hsieh, B.J., Ash, J.E., Knnedy, J.M., McLennan, G.A., Pan, Y.C. (1985) Structural Response of Large Penetrations and Closures for Containment Vessels Subjected to Loadings Beyond Design Basis. NUREG/CR-4064(SAND84-7177).
  14. Maekawa, K., Pimanmas, A., Okamura, H. (2003) Nonlinear Mechanics of Reinforced Concrete, Spon Press, London, UK.
  15. Murray, D.W. (1979) A Review of Explosive Characteristics of Prestressed Secondary Containments Near the Ultimate Load, Nuclear Engineering and Design. https://doi.org/10.1016/0029-5493(79)90017-7
  16. Murray, D.W., Chitnuyanondh L., Wong, C. (1979) Modelling and Predicting Behavior of Prestressed Concrete Secondary Containment Structures Using BOSOR5. Transactions of the 5th SMiRT, Paper 5315, Berlin, August.
  17. Petti, J.P., Spencer, B.W., Graves, H.L. (2008) Risk-Informed Assessment of Degraded Containment Vessels, Nuclear Engineering and Design, 238, pp.2038-2047. https://doi.org/10.1016/j.nucengdes.2007.10.025
  18. SIMULIA (2008) ABAQUS/Standard 6.8-1 - User's Manual, Hibbitt, Karlsson & Sorensen, Inc., RI, USA.