Journal of the Earthquake Engineering Society of Korea (한국지진공학회논문집)

Earthquake Engineering Society of Korea (한국지진공학회)
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Multi-Layered Shell Model and Seismic Limit States of a Containment Building in Nuclear Power Plant Considering Deterioration and Voids

열화 및 공극을 고려한 원전 격납건물의 다층쉘요소모델과 내진성능 한계상태

  • Nam, Hyeonung (Department of Civil Engineering, Kookmin University) ;
  • Hong, Kee-Jeung (Department of Civil Engineering, Kookmin University)
  • 남현웅 (국민대학교 건설시스템공학부) ;
  • 홍기증 (국민대학교 건설시스템공학부)
  • Received : 2024.05.30
  • Accepted : 2024.06.10
  • Published : 2024.07.01
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Abstract

For the OPR1000, a standard power plant in Korea, an analytical model of the containment building considering voids and deterioration was built with multilayer shell elements. Voids were placed in the vulnerable parts of the analysis model, and the deterioration effects of concrete and rebar were reflected in the material model. To check the impact of voids and deterioration on the seismic performance of the containment building, iterative push-over analysis was performed on four cases of the analytical model with and without voids and deterioration. It was found that the effect of voids with a volume ratio of 0.6% on the seismic performance of the containment building was insignificant. The effect of strength reduction and cross-sectional area loss of reinforcement due to deterioration and the impact of strength increase of concrete due to long-term hardening offset each other, resulting in a slight increase in the lateral resistance of the containment building. To determine the limit state that adequately represents the seismic performance of the containment building considering voids and deterioration, the Ogaki shear strength equation, ASCE 43-05 low shear wall allowable lateral displacement ratio, and JEAC 4601 shear strain limit were compared and examined with the analytically derived failure point (ultimate point) in this study.

Keywords

Acknowledgement

본 연구는 국토교통부/국토교통과학기술진흥원의 지원으로 수행되었음(과제번호 22RMPP-C163162-02).

References

  1. Nuclear Safety And Security Commission, Results of the inspection of the source of voids in the containment building of Hanbit 3-4, 160th; c2022.
  2. Lee NH, Song KB. Seismic capability evaluation of the prestressed /reinforced concrete containment, Yong-gwang nuclear pover plant Units 5 and 6. Nuclear Engineering and Design. 1991;192(2-3): 189-203. https://doi.org/10.1016/S0029-5493(99)00108-9
  3. Choi IK, Choun YS, Ahn SM, Seo JM. Probabilistic seismic risk analysis of CANDU containment structure for near-fault earthquakes. Korea Atomic Energy Research Institute, Republic of Korea. Nuclear Engineering and Design. 2008;238:1382-1391.
  4. Nguyen DD, Yhusan B, Park H, Azad MS, Lee TH. Efficiency of various structural modeling schemes on evaluating seismic performance and fragility of APR1400 containment building. Nuclear Engineering and Technology. 2021;53(8):2696-2707. https://doi.org/10.1016/j.net.2021.02.006
  5. Nakamura N, Akita S, Suzuki T, Koba M, Nakamura S, Nakano T. Study of ultimate seismic response and fragility evaluation of nuclear power building using nonlinear three-dimensional finite element model. Nuclear Engineering and Design. 2010;240(1):166-180. https://doi.org/10.1016/j.nucengdes.2009.10.018
  6. Ogaki Y. Shear strength tests of prestressedconcrete containment velssels. In Structural Mechanics in Reactor Technology J(a); c1981.
  7. Mandal TK, Ghosh S, Pujari NN. Seismic fragility analysis of a typical Indian PHWR containment: Comparison of fragility models. Structural Safety. 2016;58:11-19. https://doi.org/10.1016/j.strusafe.2015.08.003
  8. Luu HC, Mo YL, Hsu TT, Wu CL. FE simulation of cylindrical RC containment structures under reserved cyclic loading. Engineering Structures. 2019;179:255-267. https://doi.org/10.1016/j.engstruct.2018.10.050
  9. Moon IH, Kim DY, Lee KK, Kim JM. Kim HK, Seismic analysis of nuclear power plant structures under beyond-design basis earthquake excitation. International Conference on Structural Mechanics in Reactor Technology; 2022 Jul 10-15; Berlin/Postsdam, Germany. Division V; c2022.
  10. Nuclear Safety And Security Commission, Results of the inspection on the source of voids in the containment building of Hanbit Unit 3 and 4, 162nd; c2022.
  11. Nuclear Safety And Security Commission, Additional explanatory material on the structural integrity assessment of the Hanbit Unit 4 containment building, 162nd; c2022.
  12. Kato M, Tamura S, Watanabe Y, Takeda T, Nakayama T, Omote Y. Dynamic and Static Loading Tests on 1/30 Scale Model of Prestressed Concrete Containment Vessel. In Structural Mechanics in Reactor Technology K(b); c1981.
  13. Park JH, Choun YS and Choi IK. Sensitivity analysis of parameters affecting seismic response for RC shear wall with age-related degradation. Computational Structural Engineering Institute of Korea. 2011;24(4):391-398.
  14. Choe DE, Gardoni P, Rosowsky D, Haukaas T. Probabilistic capacity models and seismic fragility estimates for RC columns subject to corrosion. Reliability Engineering and System Safety. 2008;93(3): 383-393. https://doi.org/10.1016/j.ress.2006.12.015
  15. American Society of Civil Engineers (ASCE). ASCE Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities (ASCE/SEI 43-05); c2005.
  16. Nuclear Standard Committee of Japan Electric Association, Technical Code for Aseismic Design of Nuclear Power Plants. Japan Electric Association Code (JEAC 4016); c2015.
  17. Korea Atomic Energy Research Institude (KAERI). Technical Guide for Seismic Fragility Analysis of NPP Structures and Equipments. (KAERI/TR-207132002); c2002.
  18. Kim CY, Shin MS. Seismic Fragility Analysis on Nuclear Containment Structure considering the Material Degradation. Journal of the Korea Concrete Institute. 2022 Jun;34(3):291-298. https://doi.org/10.4334/JKCI.2022.34.3.291
  19. Noh SH, Jung RY, Kim ST, Lim SJ. The Structural Integrity Test for a PSC Containment with Unbonded Tendons and Numerical Analysis I. Computational Structural Engineering Institute of Korea. 2015 Oct;28(5):523-533. https://doi.org/10.7734/COSEIK.2015.28.5.523