Numerical simulation of control rod drop sensibility under different flow rates

被引:0
|
作者
Ma, Chao [1 ]
Chen, Ping [1 ]
Xiao, Zhong [1 ]
Ru, Jun [1 ]
Pu, Zengping [1 ]
Li, Yun [1 ]
机构
[1] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu
来源
Hedongli Gongcheng/Nuclear Power Engineering | 2015年 / 36卷
关键词
Chinese advanced fuel assembly; Control rod drop; CRAC program; Flow rate per loop; Numerical simulation;
D O I
10.13832/j.jnpe.2015.S2.0090
中图分类号
学科分类号
摘要
The CRAC program was adopted to simulate the control rod drop process in the Chinese advanced fuel assembly under different flow rates. The comparison of the calculation results with the test results showed good agreement. The total rod drop time decreases with the decreasing of the flow rate; the calculation values for the largest and smallest drop time are very close to the test values; and the nominal calculation curve is close to the experiment curve. © 2015, Editorial Office of Nuclear Power Engineering. All right reserved.
引用
收藏
页码:90 / 92
页数:2
相关论文
共 3 条
  • [1] Design and construction rules for fuel assemblies of PWR nuclear power plants, (2005)
  • [2] Yoon K.H., Kim J.Y., Lee K.H., Et al., Control rod drop analysis by finite element method using fluid-structure interaction for a pressurized water reactor power plant, Nuclear Engineering and Design, 239, pp. 1857-1861, (2009)
  • [3] Structural behavior of fuel assemblies for water cooled reactors, (2005)