Full Text:   <3887>

Summary:  <1960>

CLC number: TU393.3

On-line Access: 2017-06-05

Received: 2016-02-10

Revision Accepted: 2016-10-04

Crosschecked: 2017-05-15

Cited: 0

Clicked: 5277

Citations:  Bibtex RefMan EndNote GB/T7714

 ORCID:

Jia-chuan Yan

http://orcid.org/0000-0002-2781-9046

-   Go to

Article info.
Open peer comments

Journal of Zhejiang University SCIENCE A 2017 Vol.18 No.6 P.467-486

http://doi.org/10.1631/jzus.A1600136


Modular construction mechanics of a European pressurized reactor steel containment liner


Author(s):  Jia-chuan Yan, Xiao-fei Jin, Feng Qin, Zheng Li, Feng Fan, Jin-ping Ou

Affiliation(s):  Key Lab of Structures Dynamic Behavior and Control of the Ministry of Education, Harbin Institute of Technology, Harbin 150090, China; more

Corresponding email(s):   jiachuanyan@163.com

Key Words:  Containment, Construction mechanics, Steel liner, Overlapping element, Birth-death element


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.

欧洲压水堆核电站安全壳钢衬里模块化施工力学研究

目的:以广东台山欧洲压水堆(EPR)核电站安全壳钢衬里结构为研究背景,提炼钢衬里结构模块化施工全过程中的关键力学问题,对钢衬里结构模块化施工技术从力学角度给出建议,对确定结构施工方案和保证结构施工安全具有实用参考价值。
创新点:1. 提炼出EPR核电站安全壳钢衬里结构模块化施工全过程中的关键力学问题;2. 采用"重叠单元和生死单元"技术模拟大型复杂结构混凝土浇筑成型全过程。
方法:1. 通过精细化有限元分析,开展吊装工装结构优化分析、吊耳节点多尺度有限元分析和工作风速分析;2. 建立安全壳结构复杂实体有限元模型,分析模块之间对接拼装初内力、新浇筑混凝土侧压力、不均匀温度作用及风荷载等施工因素对筒体钢衬里的影响;3. 采用"重叠单元和生死单元"技术,分析大跨度穹顶钢衬里结构在混凝土浇筑成型全过程中的结构变形和应力;4. 考虑结构初始几何缺陷和材料弹塑性的影响,对混凝土浇筑成型过程中穹顶钢衬里结构进行稳定性分析。
结论:1. 采用三角形环形桁架吊装工装,能够满足吊装过程的应力和变形要求,并减少吊装工装用钢量;2. 获得了筒体钢衬里模块高度和混凝土一次浇筑最大高度的相关曲线;3. 得到了混凝土浇筑成型全过程中穹顶钢衬里结构的力学性能;4. 定义并验算了混凝土浇筑成型过程中穹顶钢衬里结构两个关键阶段的稳定性,为此类结构施工提供了理论参考。

关键词:安全壳;施工力学;钢衬里;重叠单元;生死单元

Darkslateblue:Affiliate; Royal Blue:Author; Turquoise:Article

Reference

[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.

Open peer comments: Debate/Discuss/Question/Opinion

<1>

Please provide your name, email address and a comment





Journal of Zhejiang University-SCIENCE, 38 Zheda Road, Hangzhou 310027, China
Tel: +86-571-87952783; E-mail: cjzhang@zju.edu.cn
Copyright © 2000 - 2024 Journal of Zhejiang University-SCIENCE