Transient Dynamic Characteristics Study on Reactor Coolant Pump in Variable Working Conditions

Article Preview

Abstract:

For the study of the transient hydraulic characteristics and internal flow mechanism of the reactor coolant pump from designed conditions to off-designed conditions, using CFX software to simulate the variable flow transient characteristics of reactor coolant pump impeller passageway. The results show that: during the flow transition, the radial force of the impeller doesn’t rotate around the coordinates origin, but rotates around some point in the fourth quadrant, and radial forces of the guide vanes mainly distributes in the first and second quadrant, and radial forces of the volute completely distribute in the fourth quadrant. Because of the influence from the blade number, radial forces of the impeller and guide vanes are in obvious star distribution, meanwhile, because the pump body uses annular structure,the flow and velocity in the impeller passageway and the pressure distribution of the impeller export asymmetry radial force. During the transition to big flow, the radial force impact of the impeller and guide vane mainly shows in the direction of the offset and slightly decreasement of the change magnitude. The radial force on the volute moves down with the incensement of the flow, and the changes magnitude become larger. During the transition to small flow, radial forces bearing on impellers, guide vanes and the volute, whether on the size, direction or the change magnitude, have a significant change.

You might also be interested in these eBooks

Info:

Periodical:

Pages:

258-264

Citation:

Online since:

December 2012

Export:

Price:

Permissions CCC:

Permissions PLS:

Сopyright:

© 2013 Trans Tech Publications Ltd. All Rights Reserved

Share:

Citation:

[1] Pave1 Ornahe,Ferdinand Gubina. Simulations and field tests of a reactor coolant pump emergency start-up by means of remote gas units [J], Transactions on Energy Conversion, 1992, 7( 4): 691-697.

DOI: 10.1109/60.182652

Google Scholar

[2] GaoHong, GaoFeng. Transient flow analysis in reactor coolant pump systems during flow coastdown period; Nuclear Engineering and Design, 2011, 241(2): 509-514.

DOI: 10.1016/j.nucengdes.2010.09.033

Google Scholar

[3] Liu Xia-Jie, Liu Junsheng. Test study on safety features of station blackout accident for nuclear main pump; Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2009, 43(5): 448-451.

Google Scholar

[4] Araya, Fumimasa. Transient analysis for design of primary coolant pump adopted to passive safety reactor JPSR;Journal of Nuclear Science and Technology, 1995, 32(10): 1039-1046.

DOI: 10.1080/18811248.1995.9731812

Google Scholar

[5] Tsukamoto H, Ohashi H. Transient characteris-tics of a centrifugal pump during starting period [J]. ASME Journal of Fluid Engineering, 1982, 104(1): 6- 13.

DOI: 10.1115/1.3240859

Google Scholar

[6] Tsukamoto H, Matsunaga S, Yoneda H, etal. Transient characteristics of a centrifugal pump during stopping period [J]. ASME Journal of Fluid Engineering, 1986, 108(4): 392-399.

DOI: 10.1115/1.3242594

Google Scholar

[7] Lefebvre Pj, Barker Wp. Centrifugal pump performance during transient operation [J]. ASME Journal of Fluid Engineering, 1995, 117(2): 123-128.

DOI: 10.1115/1.2816801

Google Scholar

[8] Li Yibin, Zhao Weiguo, Wang Xiuyong. Analysis and Numeric Simulation of Off-design Flow Field in Centrifugal Pump [J]. Journal of Lanzhou University of Technology, 2007,33(6): 43-46.

Google Scholar

[9] Liu Zhansheng, Liu Quanzhong, Wang Hongjie. Analysis of off-design flow fields in centrifugal pumps and hydrodynamic forces on impellers [J]. Journal of Harbin Engineering University, 2008, 29(12). 1304-1308.

Google Scholar