CLC number: TU393.3
On-line Access: 2024-08-27
Received: 2023-10-17
Revision Accepted: 2024-05-08
Crosschecked: 2017-05-15
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Jia-chuan Yan, Xiao-fei Jin, Feng Qin, Zheng Li, Feng Fan, Jin-ping Ou. Modular construction mechanics of a European pressurized reactor steel containment liner[J]. Journal of Zhejiang University Science A, 2017, 18(6): 467-486.
@article{title="Modular construction mechanics of a European pressurized reactor steel containment liner",
author="Jia-chuan Yan, Xiao-fei Jin, Feng Qin, Zheng Li, Feng Fan, Jin-ping Ou",
journal="Journal of Zhejiang University Science A",
volume="18",
number="6",
pages="467-486",
year="2017",
publisher="Zhejiang University Press & Springer",
doi="10.1631/jzus.A1600136"
}
%0 Journal Article
%T Modular construction mechanics of a European pressurized reactor steel containment liner
%A Jia-chuan Yan
%A Xiao-fei Jin
%A Feng Qin
%A Zheng Li
%A Feng Fan
%A Jin-ping Ou
%J Journal of Zhejiang University SCIENCE A
%V 18
%N 6
%P 467-486
%@ 1673-565X
%D 2017
%I Zhejiang University Press & Springer
%DOI 10.1631/jzus.A1600136
TY - JOUR
T1 - Modular construction mechanics of a European pressurized reactor steel containment liner
A1 - Jia-chuan Yan
A1 - Xiao-fei Jin
A1 - Feng Qin
A1 - Zheng Li
A1 - Feng Fan
A1 - Jin-ping Ou
J0 - Journal of Zhejiang University Science A
VL - 18
IS - 6
SP - 467
EP - 486
%@ 1673-565X
Y1 - 2017
PB - Zhejiang University Press & Springer
ER -
DOI - 10.1631/jzus.A1600136
Abstract: A European pressurized reactor (EPR) steel containment liner structure is comprised of the cylinder part and the dome part. An introduction of the steel liner structure is presented, followed by studies on the key mechanical features of the construction process using a refined finite element method. The steel liner was divided into several modules and then assembled during construction. Firstly, the equipment structure used to hoist the liner module was optimized, the lifting lug was analyzed using a multi-scale finite element model; the wind speed limit during lifting was also studied. Subsequently, the effect of internal forces during assembly between the liner modules, the lateral pressure of fresh concrete, the non-uniform temperature load, and the wind load on the cylinder module was analyzed. According to the time-varying structural performance during continuous concrete pouring and the hardening construction, an “overlapping element and birth-death element” technique was adopted to analyze the deformation and stress of the long-span steel dome liner. In addition, the stability-bearing capacities of the dome structure during construction were also studied, which took into consideration the effect of the initial geometrical imperfections and the elasto-plasticity of the material. This study presents a reference in terms of the mechanics of the construction scheme and the safety of such a type of structure.
[1]ABAQUS Inc., 2012. Abaqus Theory Manual, Release 6.12. ABAQUS Inc.
[2]Anderson, P., 2005. Thirty years of measured prestress at Swedish nuclear reactor containments. Nuclear Engineering and Design, 235(21):2323-2336.
[3]ANSYS Inc., 2012. Ansys Theory Manual, Release 14.5. ANSYS Inc.
[4]ASME (American Society of Mechanical Engineers), 2015. BPVC Section III-Rules for Construction of Nuclear Facility Components-Division 2-Code for Concrete Containments, BPVC-III-2. ASME.
[5]ASN (French Nuclear Safety Authority), 2015. EPR Information Letter No. 17: ASN Monitoring of the Flamanville EPR Reactor Construction Site: Notable Points. ASN. http://www.french-nuclear-safety.fr/Inspections/Supervision-of-the-epr-reactor/ASN-s-supervision-of-the-Flamanville-3-reactor-construction-EPR-News/EPR-Information-Letter-No.17#bottom
[6]Basha, S.M., Singh, R.K., Patnaik, R., et al., 2003. Predictions of ultimate load capacity for pre-stressed concrete containment vessel model with BARC finite element code ULCA. Annals of Nuclear Energy, 30(4):437-471.
[7]Becue, P., Barre, F., Arbez, P., 2005. Design of the EPR containment. International Association for Bridge and Structural Engineering, 90(9):85-92.
[8]CEN (European Committee for Standardization), 2003. Flat Products Made of Steels for Pressure Purposes. Part 2: Non-alloy and Alloy Steels with Specified Elevated Temperature Properties, BS EN 10028-2:2003. CEN.
[9]CEN (European Committee for Standardization), 2004. European Standard. 2: Design of Concrete Structures. Part 1-1: General Rules and Rules for Buildings, BS EN 1992-1-1:2004. CEN.
[10]CEN (European Committee for Standardization), 2005. European Standard. 3: Design of Steel Structures. Part 1-1: General Rules and Rules for Buildings, BS EN 1993-1-1:2005. CEN.
[11]CEN (European Committee for Standardization), 2007. European Standard. 3: Design of Steel Structures. Part 1-6: Strength and Stability of Shell Structures, BS EN 1993-1-6:2007. CEN.
[12]de Clercq, G., 2014. EDF Hopes French EPR will Launch before Chinese Reactors. Reuters. http://af.reuters.com/article/commoditiesNews/idAFL6N0Q665C20140731?sp=true
[13]Enformable Nuclear News, 2011. Photos of the China’s Lifting of Dome at Taishan Nuclear Power Plant. Enformable Nuclear News. http://enformable.com/2011/10/photos-of-the-chinas-lifting-of-dome-at-taishan-nuclear-power-plant/
[14]Fib Task Group on Containment Structures, 2001. Nuclear Containments. International Federation for Structural Concrete.
[15]Gioncu, V., 1995. Buckling of reticulated shells state-of-the-art. International Journal of Space Structures, 10(1):1-46.
[16]Hessheimer, M.F., Klamerus, E.W., Lambert, L.D., et al., 2003. Overpressurization Test of a 1:4-scale Pre-stressed Concrete Containment Vessel Model. Technical Report No. NU-REG/CR-6810, SAND2003-0840P, Nuclear Regulatory Commission, Washington DC, USA; Sandia National Laboratories, Albuquerque, USA; Nuclear Power Engineering Corporation, Japan.
[17]Horschel, D.S., 1988. Design, Construction, and Instrumentation of a 1:6 Scale Reinforced Concrete Containment Building. Technical Report No. NUREG/CR-5083, SAND88-0030, Nuclear Regulatory Commission, Washington DC, USA; Sandia National Laboratories, Albuquerque, USA.
[18]Horschel, D.S., 1992. Experimental Results from Pressure Testing of a 1:6 Scale Nuclear Power Plant Containment. Technical Report No. NU-REG/CR-5121, SAND88-0906, Nuclear Regulatory Commission, Washington DC, USA; Sandia National Laboratories, Albuquerque, USA.
[19]Hu, H.T., Lin, J.X., 2016. Ultimate analysis of PWR pre-stressed concrete containment under long-term prestressing loss. Annals of Nuclear Energy, 87:500-510.
[20]IAEA (International Atomic Energy Agency), 2012a. Nuclear Power Reactor Details: Taishan-1. Power Reactor Information System. https://www.iaea.org/PRIS/CountryStatistics/ReactorDetails.aspx?current=918
[21]IAEA (International Atomic Energy Agency), 2012b. Nuclear Power Reactor Details: Taishan-2. Power Reactor Information System. https://www.iaea.org/PRIS/CountryStatistics/ReactorDetails.aspx?current=919
[22]Kim, S.H., Choi, M.S., Joung, J.Y., et al., 2013. Long-term reliability evaluation of nuclear containments with tendon force degradation. Nuclear Engineering and Design, 265:582-590.
[23]Kwak, H.G., Kwon, Y., 2016. Nonlinear analysis of containment structure based on modified tendon model. Annals of Nuclear Energy, 92:113-126.
[24]Lapp, C.W., Golay, M.W., 1997. Modular design and construction techniques for nuclear power plants. Nuclear Engineering and Design, 172(3):327-349.
[25]Lee, H.P., Choun, Y.S., Seo, J.M., 2004. Nonlinear finite element analysis of containment vessel by considering the tension stiffening effect. Journal of the Korean Nuclear Society, 36(6):512-527.
[26]Lundqvist, P., Nilsson, L.O., 2011. Evaluation of prestress losses in nuclear reactor containments. Nuclear Engineering and Design, 241(1):168-176.
[27]Marques, J.G., 2010. Evolution of nuclear fission reactors: third generation and beyond. Energy Conversion and Management, 51(9):1774-1780.
[28]MOHURD (Ministry of Housing and Urban-Rural Development), 2003. Code for Design of Steel Structures, GB50017-2003. National Standards of People’s Republic of China (in Chinese).
[29]MOHURD (Ministry of Housing and Urban-Rural Development), 2008. Technical Code for Safety of Forms in Construction, JGJ 162-2008. Construction Industry Standards of People’s Republic of China (in Chinese).
[30]MOHURD (Ministry of Housing and Urban-Rural Development), 2009. Code for Construction of Mass Concrete, GB50496-2009. National Standards of People’s Republic of China (in Chinese).
[31]MOHURD (Ministry of Housing and Urban-Rural Development), 2010. Technical Specification for Space Frame Structures, JGJ 7-2010. Construction Industry Standards of People’s Republic of China (in Chinese).
[32]MOHURD (Ministry of Housing and Urban-Rural Development), 2012a. Load Code for the Design of Building Structures, GB 50009-2012. National Standards of People’s Republic of China (in Chinese).
[33]MOHURD (Ministry of Housing and Urban-Rural Development), 2012b. Specification for Design of Reinforced Concrete Shell Structures, JGJ 22-2012. Construction Industry Standards of People’s Republic of China (in Chinese).
[34]Nuclear Engineering International, 2009. Olkiluoto 3 Reactor Building Gets Roof. Global Trade Media, Progressive Media Group Limited.
[35]Parmar, R.M., Singh, T., Thangamani, I., et al., 2014. Over-pressure test on barcom pre-stressed concrete containment. Nuclear Engineering and Design, 269:177-183.
[36]People’s Daily, 2009. Taishan Nuclear Power Plant to Be One of World’s Largest. People’s Daily Online. http://en.people.cn/90001/90776/90883/6849430.html
[37]Rizkalla, S.H., Macgregor, J.G., Simmonds, S.H., 1984. Prestressed concrete containment model. Journal of Structural Engineering, 110(4):730-743.
[38]Shen, S.Z., Chen, X., 1999. Stability of Reticulated Shells. Science Press, Beijing, China (in Chinese).
[39]Shokoohfar, A., Rahai, A., 2016. Nonlinear analysis of pre-stressed concrete containment vessel (PCCV) using the damage plasticity model. Nuclear Engineering and Design, 298:41-50.
[40]Timoshenko, S., Woinowsky-Krieger, S., 1959. Theory of Plates and Shells. McGraw-Hill Book Company, USA.
[41]Twidale, D., Crowder, R., 1991. Sizewell ‘B’-A one tenth scale containment model test for the UK PWR programme. Nuclear Engineering and Design, 125(1):85-93.
[42]von Riesemann, W.A., Parks, M.B., 1995. Current state of knowledge on the behavior of steel liners in concrete containments subjected to overpressurization loads. Nuclear Engineering and Design, 157(3):481-487.
[43]Wang, G.Y., 2000. On mechanics of time-varying structures. China Civil Engineering Journal, 33(6):105-108 (in Chinese).
[44]WNA (World Nuclear Association), 2010. Nuclear Power in China. WNA.
[45]WNN (World Nuclear News), 2013a. Symbolic Milestone for Finnish EPR. WNN. http://www.world-nuclear-news.org/NN-Symbolic_milestone_for_Finnish_EPR-2410134.html
[46]WNN (World Nuclear News), 2013b. Taishan Generator Stator Lift. WNN. http://www.world-nuclear-news.org/NN_Taishan_generator_lift_1110131.html
[47]Yonezawa, K., Imoto, K., Watanabe, Y., et al., 2002. Ultimate capacity analysis of 1/4 PCCV model subjected to internal pressure. Nuclear Engineering and Design, 212(1-3):357-379.
[48]Zhang, X., 2009. 900 MW PWR containment mechanical behavior characteristics during containment test. Nuclear Engineering and Design, 239(9):1647-1652.
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