Studies on the performance of the hydraulic control rod drive for the NHR-200

被引:23
作者
Bo, HL [1 ]
Zheng, WX [1 ]
Dong, D [1 ]
机构
[1] Tsing Hua Univ, Inst Nucl Energy Technol, Beijing 100084, Peoples R China
关键词
D O I
10.1016/S0029-5493(99)00200-9
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
Theoretical analysis and experimental study on the steady state property of the hydraulic control rod drive mechanism for the 200 MW nuclear heating reactor have been carried out in depth. The minimum and maximum holding flow in steady state and their changes along with temperature were identified, and the relationship between the steady state property and the design data of the control rod drive mechanism was analyzed too. A fine agreement between the analysis results and measured data has been achieved. (C) 2000 Elsevier Science S.A. All rights reserved.
引用
收藏
页码:117 / 121
页数:5
相关论文
共 2 条
[1]  
*INET, 1995, PRELIMINARY SAFETY A
[2]  
YUANQIANG W, 1990, J TSINGHUA U, V30, P29