考虑流固耦合效应的快堆堆本体抗震试验模化方法
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摘要
为准确模拟快堆堆本体中液体晃动对主容器的作用,本文建立了一种考虑流固耦合效应的快堆堆本体抗震试验模化方法,不仅保证加速度相似比严格为1,还保证了流体与结构的质量比与原堆的相同。依照上述试验模化方法,分别设计了与快堆原型比尺为1∶25(大)和1∶50(小)两个缩比试验模型。为验证上述理论方法的有效性,对这两个模型进行了地震动力学数值模拟,并比较了大模型和小模型的模拟结果。比较结果表明,大、小模型的地震动响应参数比值满足推导得到的理论准则,从而通过数值试验方法验证了上述模化方法的有效性。该模化方法可为快堆堆本体抗震试验提供理论依据。
In order to simulate the effect of the liquid sloshing of fast reactor on the main container, a scaling method for seismic test of fast reactor vessel considering fluid-structure interaction effect was created in this paper. It not only ensures the acceleration similarity ratio is strictly 1, but also ensures the mass ratio of fluid to structure is the same as that of the original reactor. On the basis of the method, two scaled-models with the scale of 1∶25(large) and 1∶50(small) for the prototype of fast reactor were designed respectively. In order to verify the validity of the above method, the numerical simulations of the two models were carried out, and the simulation results of the large model and the small model were compared. The comparison results show that the ratio of vibration motion response parameters of the large and small models meets the derived theoretical criteria. The above simulation method is proved to be valid by numerical experiments. This scaling method can provide theoretical basis for seismic test of fast reactor vessel.
In order to simulate the effect of the liquid sloshing of fast reactor on the main container, a scaling method for seismic test of fast reactor vessel considering fluid-structure interaction effect was created in this paper. It not only ensures the acceleration similarity ratio is strictly 1, but also ensures the mass ratio of fluid to structure is the same as that of the original reactor. On the basis of the method, two scaled-models with the scale of 1∶25(large) and 1∶50(small) for the prototype of fast reactor were designed respectively. In order to verify the validity of the above method, the numerical simulations of the two models were carried out, and the simulation results of the large model and the small model were compared. The comparison results show that the ratio of vibration motion response parameters of the large and small models meets the derived theoretical criteria. The above simulation method is proved to be valid by numerical experiments. This scaling method can provide theoretical basis for seismic test of fast reactor vessel.
引文
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[2] 原朵仙,马裕超.混凝土结构动力模型重力失真效应分析[J].建筑结构,2011,41(增刊):1 077-1 078.YUAN Duoxian,MA Yuchao.Analysis of gravity distortion effect of dynamic model of concrete structure[J].Building Structure,2011,41(Supp1.):1 077-1 078(in Chinese).
[3] 郑伟.关于动力极限强度模型试验中失真效应及其修正准则的探讨[J].工程抗震,1992(3):39-43.ZHENG Wei.Discussion on distortion effect and correction criterion in dynamic ultimate strength model test[J].Engineering Seismic,1992(3):39-43(in Chinese).
[4] 杨旭东.振动台模型试验若干问题的研究[D].北京:中国建筑科学研究院,2005.
[5] 杨树标,李荣华,刘建平,等.振动台试验模型和原型相似关系的理论研究[J].河北工程大学学报:自然科学版,2007(1):8-11.YANG Shubiao,LI Ronghua,LIU Jianping,et al.Theoretical study on similarity relationship between shaking table test model and prototype[J].Journal of Hebei University of Technology:Natural Science,2007(1):8-11(in Chinese).
[6] 鲁亮,吕西林.振动台模型试验中一种消除重力失真效应的动力相似关系研究[J].结构工程师,2001(4):45-48.LU Liang,LV Xilin.A study on dynamic similarity relation to eliminate gravity distortion effect in shaking table model test[J].Structural Engineer,2001(4):45-48(in Chinese).
[7] MYRILLAS K,PLANQUART P,BUCHLIN J M,et al.Small scale experiments of sloshing considering the seismic safety of MYRRHA[J].International Journal of Hydrogen Energy,2016,41(17):7 239-7 251.
[8] 党俊杰.地震作用下AP1000非能动安全壳冷却水贮存箱及屏蔽构筑物流固耦合振动特性研究[D].北京:华北电力大学,2014.
[9] 鲁亮.中国实验快堆堆本体抗震性能试验研究与分析[D].上海:同济大学,2003.
[10] SAKURAI A,KURIHARA C,NAKAGAWA M,et al.Fluid-coupled vibration analysis of reduced models of pool-type LMFBR[C]//8th International Conference on Structural Mechanics in Reactor Technology.Belgium:[s.n.],1985.
[11] FUJIMOTO S,YAMOTO S,SHIMIZU H,et al.Experimental and analytical study on seismic design of a large pool type LMFBR in Japan[C]//8th International Conference on Structural Mechanics in Reactor Technology.Belgium:[s.n.],1985.
[12] FUJITA K,ITO T,TASHIMO M,et al.Study on the seismic response of a reactor vessel of a pool type LMFBR including fluid-structure interaction[J].Nuclear Engineering and Design,1989,113(3):455-462.
[13] 李德寅,王邦楣,林亚超.结构模型试验[M].北京:科学出版社,1996.
[14] 李之光.相似与模化[M].北京:国防工业出版社,1982.
[15] MA D C.Hydrodynamic response of viscous fluids under seismic excitation[C]//12th International Conference on Structural Mechanics in Reactor Technology.Germany:[s.n.],1991.