A vibration countermeasure for a reactor core cooling system through the use of the mechanical design parameters

机译：通过使用机械设计参数，对反应堆芯冷却系统的振动对策

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In a recent research, the authors of this paper have proposed a non-linear model to simulate vibration in the reactor core cooling system. The model describes the industrial system used in the Egyptian 2nd research reactor. It has overcome the shortcoming of the conventional model, and proved accurate simulation of the reactor core cooling mechanical system. Based on this model, this paper presents a novel vibration countermeasure using the mechanical design parameters for different spring constant and inertia's within recommended industrial constraints.

机译：在最近的研究中，本文的作者提出了一种非线性模型来模拟反应堆芯冷却系统中的振动。该模型描述了埃及2 ^{ND 研究反应堆中使用的工业系统。它克服了传统模型的缺点，并证明了反应堆芯冷却机械系统的精确模拟。在此模型的基础上，本文采用了不同弹簧常数和惯性的机械设计参数提出了一种新颖的振动对策。}

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《International Middle East Power Systems Conference》|2006年||共9页
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正文语种
中图分类电力系统的自动化;
关键词
centrifugal pump; flywheel; induction motor; shaft coupling;

机译：离心泵;飞轮;感应电动机;轴联轴器;

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机译：日本商品化快速反应器循环系统的当前可行性研究中钠冷却器的高级Mox核心设计研究
2. Optimal design of a Small Modular Reactor core with dual cooled annular fuel based on the neutronics and natural circulation parameters [J] . Nuclear Engineering and Design . 2020,第Apra期

机译：基于中子学和自然循环参数的带有双冷却环形燃料的小型模块化反应堆堆芯的优化设计
3. Seismic Response of High Temperature Gas-Cooled Reactor Core with Block-Type Fuel, (III)Vibration Experiment of Two-Dimensional Vertical Slice Core Model [J] . Takeshi IKUSHIMA, Toshiaki HONMA Journal of nuclear science and technology . 1981,第7期

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4. A vibration countermeasure for a reactor core cooling system through the use of the mechanical design parameters [C] . Kutb S. A., Abdel-Hamid A. M., Mansour A. E. Power Systems Conference, 2006. MEPCON 2006 . 2006

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5. Safety and core design of large liquid-metal cooled fast breeder reactors [D] . Qvist, Staffan Alexander 2013

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6. Physical effects of mechanical design parameters on photon sensitivity and spatial resolution performance of a breast-dedicated PET system [O] . V. C. Spanoudaki, F. W. Y. Lau, A. Vandenbroucke, -1

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7. REMI/HEAT COOL, a model for evaluation of core heat-up and emergency core spray cooling system performance for light-water-cooled nuclear power reactors [O] . Munthe Andersen J.G. 1973

机译：REmI / HEaT COOL，用于评估轻水冷却核动力堆核心加热和应急堆芯喷雾冷却系统性能的模型

A vibration countermeasure for a reactor core cooling system through the use of the mechanical design parameters

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