预应力混凝土安全壳模型施工期和后续使用性能分析
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摘要
安全壳结构是核电站的一道重要安全屏障,其在施工期和后续使用期间的安全性备受关注。通过商业有限元软件ABAQUS建立安全壳结构模型(缩尺比例1∶3)研究在自重、混凝土收缩、预应力以及设计基准内压等荷载作用下安全壳的应力发展、变形情况以及开裂行为。计算结果表明,混凝土的收缩会使得受到约束的壳体底部大体积混凝土开裂。施加预应力后,孔洞周围混凝土会产生裂缝。在基准内压荷载作用下,部分裂缝会进一步扩展和延伸,但其他主体结构部分并未开裂。预应力钢筋的Von Mises应力有所增加,但并未达到钢材的屈服强度。研究结果可用于指导现有核电站的设计和施工。
The nuclear containment is an essential barrier of the nuclear power plant,and its structural safety during construction and service life is notable. In this study,a 1 ∶ 3 scaled nuclear containment model was developed by using a commercial software ABAQUS based on the finite element method to investigate the performance of the containment subjected to gravity,concrete shrinkage,prestressing and internal design basis pressure. The numerical simulation results indicate that concrete shrinkage caused the restrained bottom mass concrete cracking. Cracks also took place around some containment holes after prestressing. Some cracks propagated under the internal design basis pressure,but other parts remained intact. The Von Mises stresses of most prestressed bars increased,but did not reach the yielding strength. The research results could provide reference for the design and construction of nuclear containments.
The nuclear containment is an essential barrier of the nuclear power plant,and its structural safety during construction and service life is notable. In this study,a 1 ∶ 3 scaled nuclear containment model was developed by using a commercial software ABAQUS based on the finite element method to investigate the performance of the containment subjected to gravity,concrete shrinkage,prestressing and internal design basis pressure. The numerical simulation results indicate that concrete shrinkage caused the restrained bottom mass concrete cracking. Cracks also took place around some containment holes after prestressing. Some cracks propagated under the internal design basis pressure,but other parts remained intact. The Von Mises stresses of most prestressed bars increased,but did not reach the yielding strength. The research results could provide reference for the design and construction of nuclear containments.
引文
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[4]孙锋,潘蓉,王璐,等.设计基准内压下混凝土安全壳的有效预应力作用研究[J].核安全,2013,12(3):20-25.Sun Feng,Pan Rong,Wang Lu,et al.Study on effective prestressing effects on concrete containment under the design-basis pressure condition[J].Nuclear Safety,2013,12(3):20-25.(in Chinese)
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[6]赵超超,李忠诚,董占发.CPR1000安全壳结构极限承载能力分析[J].计算机辅助工程,2013,22(A02):393-399.Zhao Chaochao,Li Zhongcheng,Dong Zhanfa.Ultimate bearing capacity analysis on containment structure of CPR1000[J].Computer Aided Engineering,2013,22(A02):393-399.(in Chinese)
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[8]ABAQUS/Standard User's Manual,Version 6.11[M].Dassault Systèmes Simulia Corporation,2011.
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[10]顾祥林.混凝土结构基本原理[M].上海:同济大学出版社,2012.Gu Xianglin.Basic principles of concrete structures[M].Shanghai:Tongji University Press,2012.(in Chinese)
[11]顾嘉丰,任青文.水工混凝土弥散型裂缝数值模型中开裂判据的研究[J].工程力学,2015(6):84-91.Gu Jiafeng,Ren Qingwen.Study on hydraulic cracking criterion in smeared crack numerical model[J].Engineering Mechanics,2015(6):84-91.(in Chinese)
[2]孟剑,杨景龙.安全壳极限承载力中预应力的数值模拟[J].工业建筑,2011,41(1):127-131.Meng Jian,Yang Jinglong.The prestress numerical simulation in the research of the ultimate bearing capacity of containment of nuclear power plant[J].Industrial Construction,2011,41(1):127-131.(in Chinese)
[3]李振宝,林树潮,王冬雁,等.某核电站安全壳预应力施工模拟分析[J].工业建筑,2014,5:024.Li Zhenbao,Lin Shuchao,Wang Dongyan,et al.Prestressed tendon construction analysis of containment for a nuclear power plant[J].Industrial Construction,2014,5:024.(in Chinese)
[4]孙锋,潘蓉,王璐,等.设计基准内压下混凝土安全壳的有效预应力作用研究[J].核安全,2013,12(3):20-25.Sun Feng,Pan Rong,Wang Lu,et al.Study on effective prestressing effects on concrete containment under the design-basis pressure condition[J].Nuclear Safety,2013,12(3):20-25.(in Chinese)
[5]陈勤,钱稼茹.内压荷载下安全壳1:10模型结构非线性有限元分析[J].工程力学,2002,19(6):73-77.Chen Qin,Qian Jiaru.Nonlinear finite element analysis of 1:10 containment model structure subjected to internal pressure[J].Engineering Mechanics,2002,19(6):73-77.(in Chinese)
[6]赵超超,李忠诚,董占发.CPR1000安全壳结构极限承载能力分析[J].计算机辅助工程,2013,22(A02):393-399.Zhao Chaochao,Li Zhongcheng,Dong Zhanfa.Ultimate bearing capacity analysis on containment structure of CPR1000[J].Computer Aided Engineering,2013,22(A02):393-399.(in Chinese)
[7]Hu H T,Liang J I.Ultimate analysis of BWR Mark III reinforced concrete containment subjected to internal pressure[J].Nuclear Engineering and Design,2000,195(1):1-11.
[8]ABAQUS/Standard User's Manual,Version 6.11[M].Dassault Systèmes Simulia Corporation,2011.
[9]中华人民共和国住房和城乡建设部.GB 50010—2010混凝土结构设计规范[S].中国建筑工业出版社,2010.Ministry of Housing and Urban-Rural Construction of the People's Republic of China.GB 50010—2010Code for design of concrete structures[S].Beijing:China Architecture and Building Press,2010.(in Chinese)
[10]顾祥林.混凝土结构基本原理[M].上海:同济大学出版社,2012.Gu Xianglin.Basic principles of concrete structures[M].Shanghai:Tongji University Press,2012.(in Chinese)
[11]顾嘉丰,任青文.水工混凝土弥散型裂缝数值模型中开裂判据的研究[J].工程力学,2015(6):84-91.Gu Jiafeng,Ren Qingwen.Study on hydraulic cracking criterion in smeared crack numerical model[J].Engineering Mechanics,2015(6):84-91.(in Chinese)