Fast Reactor Core Seismic Analysis for Verification of Assessment Model Considering Deformation of Core Elements

Shinichiro Matsubara, Akihisa Iwasaki, K. Kawamura, Hidenori Harada, Tomohiko Yamamoto
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Abstract

To design fast reactor (FR) core components, seismic response must be evaluated in order to ensure structural integrity. Thus, a core seismic analysis method has been developed to evaluate 3D core vibration behavior considering fluid structure interaction and vertical displacements (rising). The analysis code is verified by a series of vibration tests. The evaluation model to simulate the influence of core element deformation due to heat and irradiation were developed and the analysis of the seismic test was performed. And the evaluation model was verified by comparing the seismic test and analysis results. A fast reactor core consists of hundreds of core elements, which lengthen due to thermal expansion and swelling. So, the core elements are self-standing on the core support structure and not restrained in the axial direction. When the vertical seismic excitation surpasses gravitational acceleration, it is necessary to consider vertical displacements and horizontal displacements of the core elements simultaneously. This 3-D vibration behavior is affected by the fluid loads from ambient coolant and the interference of surrounding structures. To solve this, the influential factors to vibration behaviors due to the structure and fluid body, including fluid structure interaction, are extracted and the 3-D reactor core group vibration analysis code (REVIAN-3D) is developed. Core elements are deformed due to thermal expansion and irradiation, and are interfered with surrounding elements each other. The interference increases the frictional force acting on the core element and reduce the vertical displacement (rising) of the core element during the earthquake. To evaluate this reduction of rising, the evaluation model simulating this deformation is incorporated in REVIAN-3D. In this study, the analysis of the vibration test was carried out using the new incorporated evaluation model. As the deformation of mock-up increases, the vertical displacement (rising) decreases, and when the initial interference due to deformation exceeds the threshold, no rising occurs. This trend agreed well between the vibration test and analysis. It is verified that the new incorporated evaluation model simulates the test result enough.
考虑堆芯构件变形的快堆堆芯地震分析验证
在设计快堆堆芯构件时,必须对堆芯构件进行地震响应评估,以保证堆芯结构的完整性。因此,开发了一种岩心地震分析方法,以评估考虑流体-结构相互作用和垂直位移(上升)的三维岩心振动行为。通过一系列振动试验验证了分析代码的正确性。建立了模拟热辐射对岩心构件变形影响的评价模型,并进行了地震试验分析。并通过地震试验与分析结果的对比,对评价模型进行了验证。一个快堆堆芯由数百个核心元件组成,这些核心元件由于热膨胀和膨胀而延长。因此,核心元件在核心支撑结构上是独立的,在轴向上不受约束。当竖向地震激励超过重力加速度时,需要同时考虑岩心构件的竖向位移和水平位移。这种三维振动特性受到环境冷却剂流体载荷和周围结构干扰的影响。为解决这一问题,提取了结构和流体对堆芯振动行为的影响因素,包括流固耦合作用,开发了三维堆芯组振动分析程序(revan - 3d)。核心元件由于热膨胀和辐照而发生变形,并与周围元件相互干扰。干涉增大了作用在芯件上的摩擦力,减小了芯件在地震过程中的垂直位移(上升)。为了评估这种减少上升,在revan - 3d中加入了模拟这种变形的评估模型。在本研究中,采用新纳入的评价模型对振动试验进行了分析。随着实体变形的增大,竖向位移(上升)减小,当变形引起的初始干涉超过阈值时,竖向位移(上升)不再发生。振动试验与分析结果吻合较好。结果表明,所建立的综合评价模型能较好地模拟试验结果。
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