Theoretical and Numerical Modal Analysis for Nuclear Coolant Pump and its Scaled Rotor System

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Abstract:

This paper presents a theoretical transfer matrix method for the modal analysis of nuclear coolant pump, and base on certain similarity law, a scaled rotor system is designed so as to simulate the characteristics of the real nuclear coolant pump, especially the vibration characteristics. Following that, the finite element method is used to verify the accuracy of the above theoretical method since there are a few simplifications in theoretical method compared with the finite element method. Finally the natural vibration frequencies and vibration modes of both nuclear coolant pump and the designed scaled rotor system are attained, which have high similarity with each other, and which confirm the accuracy of the two methods that are used in this article.

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985-991

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December 2010

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© 2011 Trans Tech Publications Ltd. All Rights Reserved

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[1] LU Qun-xian: Reactor Primary Pumps Dynamic Balancing Test, Nuclear Power Engineering, Vol. 23. No. 3. (2002).

Google Scholar

[2] Ma Hui, Zhou Wenjian: the modal analysis of nuclear power station coolant pump, Mechanical Manufacturing, Vol. 44, No. 10.

Google Scholar

[3] Zhang Zhengkai, Zhang Qidong: The Design of Vertical Rotor-bearing System Test Rig, Lubrication Engineering, Vol. 33, No. 10.

Google Scholar

[4] Zhang Xiaolong, He Hongqing: Critical rotational speed of turbo-pump rotor (IV) transfer matrix method for the distributed mass shaft, Journal of Propulsion Technology, Apr. 2000 Vol. 21 No. 2.

Google Scholar

[5] He Hongqing, Shen Dakuan, Zhang Zhewen: Study on Critical Rotational Speed of Turbo-pump Rotors (I) The Transfer Matrix Method for Homogeneous Support Rotors, Journal of Propulsion Technology, Dec. 1998 Vol. 19 No. 6.

Google Scholar

[6] Mao Jianhua, Gong Chuanjia: The Design, Build, Operation of the Experimental Circuit for Coolant Pump in Nuclear Power Station, The Pump Technology, 1998, 04.

Google Scholar

[7] Liu Xiajie: Flow and Vibration Characteristic Research of Nuclear Main Pump under Station Blackout Accident, Shanghai, (2008).

Google Scholar

[8] Song Yanwen, Li Zaihe, Yu Lingxin, Li Cangxue: Design and Evaluation of Rotor Flying-wheel for the Pump-motor in Nuclear Plant, [J] Motor Technology, 1999, No. 5 Motor Part.

Google Scholar

[9] Andritz Stress Report No. 7, Earthquake and LOCAL Analysis of the Pump Unit[R], Order No.: 10-24726/0. Page No.: 40-43.

Google Scholar