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高温与液压对快堆座式主容器屈曲的影响

Influence of High Temperature and Hydraulic Pressure in Main Vessel of Fast Breed Reactor on Buckling Behavior
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摘要 讨论了快中子增殖反应堆在运行工况下 ,主容器内液态钠的高温和液压的存在对容器的屈曲行为的影响 .首先用有限元分析了聚氯乙烯圆柱壳容器实验模型在室温和高温、无液压和有液压时在模拟水平地震的水平力和弯矩荷载下的屈曲荷载与屈曲模态 ,高温使容器壁的弹性模量降低 ,从而使容器抗屈曲能力降低 ,而液压的存在使抗屈曲能力增加 .计算结果与实验结果吻合得很好 .然后用同一程序计算了中国实验快堆钠池主容器在室温和高温、无液压和有液压时在模拟水平地震的水平力和弯矩荷载下的静态屈曲荷载与屈曲模态 ,由于屈曲发生在主容器的裙座 ,不是在有液体的主圆柱壳上 。 The influences of the high temperature and the pressure of liquid-state sodium in the main vessel of fast breed reactor(FBR) on buckling loads and modes are discussed in this paper.At first the buckling loads and modes under various conditions such as normal temperature or high temperature and with or without pressure of liquid for test model are calculated by using finite element method (FEM) code,which is a cylindrical shell vessel made by polyvinyl chloride(PVC) and is subjected by horizontal force and moment simultaneously.These horizontal force and moment are simulated to seismic load.The calculation results are in reasonably good agreement with those obtained by test and indicate that the capacity of anti-buckle for the vessel reduces when the module of elasticity decreases due to the increase of the temperature,but the capacity of anti-buckle increases when there is the pressure of liquid.Then the static analogue to seismic loads on buckling behavior under above-mentioned various conditions for the main vessel of Chinese Experimental FBR is carried out by using the same code.The results indicate that there are few influences of the high temperature and the pressure of liquid on buckling loads and modes,because the buckle takes place on the support skirt,where there is no liquid-state sodium.
作者 沈成康 沈渊
出处 《同济大学学报(自然科学版)》 EI CAS CSCD 北大核心 2002年第3期253-257,共5页 Journal of Tongji University:Natural Science
基金 国家科学技术部'九五'攻关资助项目 '八六三'计划资助项目 ( 96-G0 1-0 2 -0 6)
关键词 座式主容器 屈曲 高温 液压 快中子增殖反应堆 有限元分析 屈曲荷载 屈曲模态 抗屈曲能力 fast breed reactor bottom-supported main vessel buckle high temperature hydraulic pressure
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参考文献4

  • 1[1]Kawamoto Y, Kodama T, Matsuura S. The effect of thermal loads on bucking strength of cylindrical shells[ A ]. Proceeding of 12th International Conference on Structural Mechanics in Reactor Technology[C]. Stuttgart: SMIRT, 1993. 269 - 274.
  • 2[2]Akiyama H,Ohtsubo H, Yamada M, et al. Oudine of the seismic buckling design guideline of FBR main vessels[ A]. Proceeding of 13th International Conference on Structural Mechanics in Reactor Technology[C]. Porto Alegre: SMIRT, 1995. 445 - 456.
  • 3[3]Akiyama H. Demonstration test and research program of buckling of FBR[A]. Proceeding of 10th International conference on Structural Mechanics in Reactor Technology[C]. Los Angeles:SMIRT, 1989. 215 - 222.
  • 4[4]Matsuura S,Nakamura H,Murakami T, et al. Shear- bending buckling strength of FBR main vessels[A]. Proceeding of 13th International Conference on Structural Mechanics in Reactor Technology [C], Porto Alegre:SMIRT, 1995. 457 -462.

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