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Failure analysis of prestressed concrete containment vessels under internal pressure considering thermomechanical coupling

Wu Yu-Xiao|Fei Zi-Jian|Feng De-Cheng|Song Meng-Yan
한국원자력학회 (Korean Nuclear Society)|2023.12|Nuclear Engineering and Technology|제55권 제12호|pp. 4504-4517|DOI 10.1016/j.net.2023.08.022

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참고문헌

키워드

Internal pressurePCCVsDamage and failureThermomechanical coupling
주제분류원자력공학

초록

After a loss of coolant accident (LOCA) in the prestressed concrete containment vessels (PCCVs) of nuclear power plants, the coupling of temperature and pressure can significantly affect the mechanical properties of the PCCVs. However, there is no consensus on how this coupling affects the failure mechanism of PCCVs. In this paper, a simplified finite element modeling method is proposed to study the effect of temperature and pressure coupling on PCCVs. The experiment results of a 1:4 scale PCCV model tested at Sandia National Laboratory (SNL) are compared with the results obtained from the proposed modeling approach. Seven working conditions are set up by varying the internal and external temperatures to investigate the failure mechanism of the PCCV model under the coupling effect of temperature and pressure. The results of this paper demonstrate that the finite element model established by the simplified finite element method proposed in this paper is highly consistent with the experimental results. Furthermore, the stress-displacement curve of the PCCV during loading can be divided into four stages, each of which corresponds to the damage to the concrete, steel liner, steel rebar, and prestressing tendon. Finally, the failure mechanism of the PCCV is significantly affected by temperature.

Abstract

After a loss of coolant accident (LOCA) in the prestressed concrete containment vessels (PCCVs) of nuclear power plants, the coupling of temperature and pressure can significantly affect the mechanical properties of the PCCVs. However, there is no consensus on how this coupling affects the failure mechanism of PCCVs. In this paper, a simplified finite element modeling method is proposed to study the effect of temperature and pressure coupling on PCCVs. The experiment results of a 1:4 scale PCCV model tested at Sandia National Laboratory (SNL) are compared with the results obtained from the proposed modeling approach. Seven working conditions are set up by varying the internal and external temperatures to investigate the failure mechanism of the PCCV model under the coupling effect of temperature and pressure. The results of this paper demonstrate that the finite element model established by the simplified finite element method proposed in this paper is highly consistent with the experimental results. Furthermore, the stress-displacement curve of the PCCV during loading can be divided into four stages, each of which corresponds to the damage to the concrete, steel liner, steel rebar, and prestressing tendon. Finally, the failure mechanism of the PCCV is significantly affected by temperature.

참고문헌 (48)

  1. J. Cobb, "Highlights of the world nuclear performance report 2020", ATW - Int. J. Nucl. Power, 65(11–12), pp.551~554 (2020)
  2. H. G. Kwak, "Numerical models for prestressing tendons in containment structures", Nucl. Eng. Des, 236(10), pp.1061~1080 (2006)
  3. K. Donten, "Tests on model of prestressed reactor containment", Archiwum Inzynierii Ladowej, 26(1), pp.231~245 (1980)
  4. Experimental Results from Pressure Testing a 1:6-scale Nuclear Power Plant containment, "Horschel", Sandia National Laboratories, ~ (1992)
  5. M. F. Hessheimer, "Functional and Structural Failure Mode Overpressurization Tests of 1: 4-Scale Prestressed Concrete Containment Vessel Model" (2003)
  6. S. Kevorkian, "Prediction of a Containment Vessel Mock-Up Cracking during over Design Pressure test" (2005)
  7. S. Jim´enez, "Analysis of the mock-up of a reactor containment building: comparison with experimental results", Nucl. Eng. Des, 359, pp.110454~ (2020)
  8. L. Charpin, "Ageing and Air Leakage Assessment of a Nuclear Reactor Containment Mock-Up: VERCORS 2nd benchmark", NUCLEAR ENGINEERING AND DESIGN, pp.377~ (2021)
  9. Y. P. Liang, "Probabilistic safety assessment of nuclear containment vessel under internal pressure considering spatial variability of material properties", Int. J. Pres. Ves. Pip, pp.200~ (2022)
  10. M. Manjuprasad, "Non-linear dynamic response of a reinforced concrete secondary containment shell subjected to seismic load", Eng. Struct, 23(5), pp.397~406 (2001)
  11. 전영선, "EVALUATION OF SEISMIC SHEAR CAPACITY OF PRESTRESSED CONCRETE CONTAINMENT VESSELS WITH FIBER REINFORCEMENT", Nuclear Engineering and Technology, 47(6), pp.756~765 (2015), 한국원자력학회
  12. 전영선, "CONTAINMENT PERFORMANCE EVALUATION OF PRESTRESSED CONCRETE CONTAINMENT VESSELS WITH FIBER REINFORCEMENT", Nuclear Engineering and Technology, 47(7), pp.884~894 (2015), 한국원자력학회
  13. Zhi Zheng, "The optimum steel fiber reinforcement for prestressed concrete containment under internal pressure", Nuclear Engineering and Technology, 54(6), pp.2156~2172 (2022), 한국원자력학회[DOI]
  14. T. de Larrard, "Effect of the Young modulus variability on the mechanical behaviour of a nuclear containment vessel", Nucl. Eng. Des, 240(12), pp.4051~4060 (2010)
  15. International Standard Problem No. 48-containment Capacity, Synthesis Report, "G. Doughty", ~ (2005)
  16. L. Tong, "Ultimate pressure bearing capacity analysis for the prestressed concrete containment", Ann. Nucl. Energy, 121, pp.582~593 (2018)
  17. T. F. Kanzleiter, "Experimental investigations of pressure and temperature loads on a containment after a loss-of-coolant accident", Nucl. Eng. Des, 38(1), pp.159~167 (1976)
  18. SANG HOON NOH, "ANALYSIS OF PRESTRESSED CONCRETE CONTAINMENT VESSEL(PCCV) UNDER SEVERE ACCIDENT LOADING", Nuclear Engineering and Technology, 40(1), pp.77~86 (2008), 한국원자력학회
  19. Zhen Zhou, "Mechanical analysis for prestressed concrete containment vessels under loss of coolant accident", Computers and Concrete, An International Journal, 14(2), pp.127~143 (2014), 사단법인 한국계산역학회
  20. Z.F. Wang, "Study on failure mechanism of prestressed concrete containments following a loss of coolant accident", ENGINEERING STRUCTURES, pp.202~ (2020)
  21. Zheng Zhi, "Investigation on damage assessment of fiber-reinforced prestressed concrete containment under temperature and subsequent internal pressure", Nuclear Engineering and Technology, 55(6), pp.2053~2068 (2023), 한국원자력학회[DOI]
  22. Yang Qingyu, "Pretest analysis of a prestressed concrete containment 1:3.2 scale model under thermal-pressure coupling conditions", Nuclear Engineering and Technology, 55(6), pp.2069~2087 (2023), 한국원자력학회[DOI]
  23. Song Jin, "Nonlinear Finite Element Analysis of Prestressed Concrete Containment Vessel under Severe Accident Loads", KSCE Journal of Civil Engineering, 24(3), pp.816~825 (2020), 대한토목학회[DOI]
  24. M. K. Chakraborty, "Assessment of Ultimate Load Capacity of concrete containment structures against structural collapse", Nucl. Eng. Des, 323, pp.417~426 (2017)
  25. D. C. Feng, "Softened damage-plasticity model for analysis of cracked reinforced concrete structures", J. Struct. Eng, 144(6) (2018)
  26. D. C. Feng, "Cyclic behavior modeling of reinforced concrete shear walls based on softened damage-plasticity model", Eng. Struct, 166, pp.363~375 (2018)
  27. "Eng. Struct", 2018, 49~66
  28. Afsin Saritas, "Analysis of RC walls with a mixed formulation frame finite element", Computers and Concrete, An International Journal, 12(4), pp.519~536 (2013), 사단법인 한국계산역학회
  29. J. Li, "Stochastic damage model for concrete based on energy equivalent strain", Int. J. Solid Struct, 46(11–12), pp.2407~2419 (2009)
  30. "Comput. Mech", 2015, 267~285
  31. D. C. Feng, "Stochastic nonlinear behavior of reinforced concrete frames. II:numerical simulation", J. Struct. Eng, 142(3) (2016)
  32. Y. P. Liang, "High-fidelity numerical analysis of the damage and failure mechanisms of a prestressed concrete containment vessel under internal pressure", Nucl. Eng. Des, pp.383~ (2021)
  33. J. Y. Wu, "An energy release rate-based plastic-damage model for concrete", Int. J. Solid Struct, 43(3–4), pp.583~612 (2006)
  34. J. Y. Wu, "Unified plastic-damage model for concrete and its applications to dynamic nonlinear analysis of structures", Struct. Eng. Mech, 25(5), pp.519~540 (2007)
  35. "Structural Journal", 1988, 624~635
  36. J. Y. Wu, "Damage Energy Release Rate-Based Elastoplastic Damage Constitutive Model for Concrete and its Application to Nonlinear Analysis of structures", Department of Building Engineering, pp.2004
  37. "Struct. Des. Tall Special Build", 2016, 578~601
  38. D. C. Feng, "Stochastic damage hysteretic model for concrete based on micromechanical approach", Int. J. Non Lin. Mech, 83, pp.15~25 (2016)
  39. J. Z. Xiao, "Review of studies on the fire-resistance behaviour of HPC structures", Ind. Constr, 31, pp.53~56 (2001)
  40. Y. Jihong, "THE EFFECTS OF HIGH TEMPERATURE ON COMPRESSIVE STRENGTH OF CONCRETE" (2002)
  41. B. Wu, "Experimental research on deformation and constitutive relationship of concrete under axial loading and high temperature", J. Build. Struct, 20(5), pp.42~49 (1999)
  42. S. M. Alogla, "Temperature-induced transient creep strain in fiberreinforced concrete", Cement Concr. Compos, 113, pp.103719~ (2020)
  43. M. Menegotto, "Method of Analysis for Cyclically Loaded RC Plane Frames Including Changes in Geometry and Non-elastic Behavior of Elements under Combined Normal Force and bending" (1973)
  44. Nonlinear Analysis of Reinforced Concrete Frames Including Bond-Slip effects, "S. Limkatanyu", ~ (2008)
  45. H. G. Kwak, "Nonlinear analysis of containment structure based on modified tendon model", Ann. Nucl. Energy, 92, pp.113~126 (2016)
  46. J. Y. Wu, "Numerical modeling and simulation of a prestressed concrete containment vessel", Ann. Nucl. Energy, 121, pp.269~283 (2018)
  47. X. D. Ren, "Fragility analysis of a prestressed concrete containment vessel subjected to internal pressure via the probability density evolution method", Nucl. Eng. Des, pp.390~ (2022)
  48. Z. Zheng, "Damage performance analysis of prestressed concrete containments following a loss of coolant accident considering different external temperatures", Ann. Nucl. Energy, pp.181~ (2023)

관련 논문AI추천

Pretest analysis of a prestressed concrete containment 1:3.2 scale model under thermal-pressure coupling conditionsFan Feng, Yang Qingyu, Yan Jiachuan한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제6호Investigation on damage assessment of fiber-reinforced prestressed concrete containment under temperature and subsequent internal pressureHuang Shuai, Pan Xiaolan, Su Chunyang, Sun Ye, Wang Yong, Zheng Zhi한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제6호Investigation on structural failure criteria and material property uncertainties of prestressed concrete containment structure우한상, 장윤석, 조우민한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제1호Experimental investigation and design method of the general anchorage zone in the ring beam of prestressed concrete containment vesselsChen Tao, Lan Tianyun, Meng Shaoping, Su Yanli, Wu Chang한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제2호A numerical approach for assessing internal pressure capacity at liner failure in the expanded free-field of the prestressed concrete containment vessel장윤석, 조우민, 하성국, 강새한솔한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제10호Reevaluation of failure criteria location and novel improvement of 1/4 PCCV high fidelity simulation model under material uncertainty quantifications손호영, 주부석한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제9호

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