Modeling analyses of two-phase flow instabilities for straight and helical tubes in nuclear power plants

被引:15
作者
Dong, Ruiting [1 ]
Niu, Fenglei [1 ]
Zhou, Yuan [2 ]
Yu, Yu [1 ]
Guo, Zhangpeng [1 ]
机构
[1] North China Elect Power Univ, Beijing Key Lab Pass Nucl Power Safety & Technol, Beijing 102206, Peoples R China
[2] Shanghai Jiao Tong Univ, Sch Nucl Sci & Engn, Shanghai 200240, Peoples R China
基金
中国国家自然科学基金;
关键词
Nuclear fuels - Control theory - Cooling - Frequency domain analysis - Two phase flow - Tubes (components);
D O I
10.1016/j.nucengdes.2016.07.001
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The effects of system pressure, mass flux and inlet subcooling on two-phase flow instability for the test section consisted of two heated straight channels or two helical channels are studied by means of RELAP5/MOD3.3 and multi-variable frequency domain control theory. The experimental data in two straight channels are used to verify the RELAP5 and multi-variable frequency domain control theory results. The thermal hydraulic behaviors and parametric effects are simulated and compared with the experimental data. The RELAP5 results show that the flow stability increases with the system pressure, mass velocity, and inlet subcooling at high subcoolings. The frequency domain theory presents the same results as those given by the time domain theory (RELAP5). The effects of system pressure, mass velocity and inlet subcooling are simulated to find the difference between the straight and the helical tube flows. The RELAP5 and the multi-variable frequency domain control theory are used in modeling and simulating density wave oscillation to study their advantages and disadvantages in straight and helical tubes. (C) 2016 Elsevier B.V. All rights reserved.
引用
收藏
页码:205 / 217
页数:13
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