首页> 外文会议>Proceedings of International Conference on Structural Mechanics in Reactor Technology >SLOSHING EFFECTS OF ADS-DF LEAD-BISMUTH PRIMARYCOOLANT CAUSED BY THE REFERENCE EARTHQUAKE
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SLOSHING EFFECTS OF ADS-DF LEAD-BISMUTH PRIMARYCOOLANT CAUSED BY THE REFERENCE EARTHQUAKE

机译:参考地震引起的ADS-DF铅-铋原液冷却剂的晃动效应

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This paper deals with the analysis of the XADS reactor vessel filled by lead bismuth eutectic covered by apressurized Argon and subjected to seismic loads characterized by various level of ground accelerations. The socalledAccelerator Driven Systems (ADS) are made up of a proton accelerator and a subcritical reactor.The main aims of the analyses are: - to investigate the effects of the coupling between internal primarycoolant and vessel, - to determine the stress level of the reactor vessel due to an Operating Basis Earthquake aswell as to a Design Basis Earthquake,- to determine the influence of coolant sloshing on the stress level of thereactor vessel.The effect of the interaction between vessel and primary coolant was determined by comparing the resultsby means of two numerical models: one in which the fluid has been simulated as lumped masses connected tothe internal nodes of the vessel and the other which considers a coupling between the vessel (simulated by meansof a Lagrangean elements ) and the fluid (simulated by means of Eulerian elements).The analyses highlighted the importance of the interaction between the fluid and the reactor vessel in termsof both the level of the stress and the distribution. The results showed that if the fluid masses are concentrated onthe internal nodes of reactor vessel the maximum stresses are underestimated and the actual point of maximumstress is not located. The point of maximum stress for this model is located near the constraint of the reactorvessel on the support structure while in the model with fluid interaction the most stressed point is at the vesselbottom.
机译:本文分析了XADS反应堆容器中填充的铅铋共晶合金覆盖的情况。 加压的氩气,并承受以不同水平的地面加速度为特征的地震载荷。所谓的 加速器驱动系统(ADS)由质子加速器和亚临界反应堆组成。 分析的主要目的是:-研究内部原发之间耦合的影响 冷却剂和容器-确定由于运行基础地震而引起的反应堆容器的应力水平 以及设计基准地震,以确定冷却液晃动对应力水平的影响。 反应堆容器。 通过比较结果来确定容器和主冷却液之间的相互作用的影响 通过两个数值模型:一个将流体模拟为连接到的集总质量 容器的内部节点以及考虑容器之间耦合的另一个节点(通过 拉格朗日元素)和流体(通过欧拉元素模拟)。 这些分析突出了流体和反应堆容器之间相互作用的重要性。 应力水平和分布水平。结果表明,如果流体质量集中在 反应堆容器内部节点的最大应力被低估了,实际的最大点 压力不在位。该模型的最大应力点位于反应堆的约束附近 血管在支撑结构上,而在具有流体相互作用的模型中,最大应力点在血管上 底部。

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