【作者】 刘爱国；

【导师】 陆道纲；

【作者基本信息】 华北电力大学（北京） ， 动力机械及工程， 2010， 硕士

【摘要】 浸没在液钠中的快堆堆芯燃料组件在地震作用下发生振动,可能导致堆内构件的损坏失效,从而影响反应堆结构完整性和安全性。堆内冷却剂流体使该振动表现为强烈的非线性,因此,研究地震引起的流固耦合效应对快堆抗震分析十分重要。本文主要通过流固耦合振动试验研究,模拟燃料组件在流体环境下的振动响应,观察流体对燃料组件振动的相互影响,得到流体对组件固有频率、阻尼、附加质量和附加阻尼的影响。并在本文中建立了与振动试验相对应的新的燃料组件流固耦合计算模型,最后通过理论值与试验值的比较证明该理论计算模型是准确的,可工程化应用。这为数值化分析快堆燃料组件的流固耦合效应提供试验数据和理论依据。更多还原

【Abstract】 Fuel assemblies of fast breeder reactor core (FBR) submerged in the liquid sodium may vibrate during the earthquake, which possibly leads components of the core to structural failure and affects structural integrity and safety qualification of the core. Coolant fluid of the reactor make the vibration of the assemblies to appear nonlinear. So, It is great important to study the seismic-induced fluid-structure interaction for seismic capability of FBR core. This paper first will be through the study of fluid-structure interaction vibration test to simulate vibraton responses of fuel assemblies under fluid environment, to observe the fluid force on the fuel assemblies, abtaining the effects of fluid on the frequency, damping, added mass and added damping. And also in this paper will propose some new and corresponding the test fluid-structure interaction calculation model of FBR fuel assemblies. The last, through the theoretical values of the calculation model compared with the experimental values to prove that fluid-structure interaction calculation model of FBR fuel assemblies is accurate, can be applied engineering. The basic work will provide experimental datas and theoretical basis for the numerical method on seismic behavior research of fast reactor fuel assembly.更多还原