Influence on natural circulation nuclear thermal coupling average power under rolling motion

被引：0
作者：
机构：
[1] National Key Discipline Laboratory of Nuclear Safety and Simulation Technology, Harbin Engineering University
[2] CGNPC Uranium Resources Corporation
[3] China Ship Development and Design Center
[4] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China
来源：
Tan, S.-C. (tansichao@hrbeu.edu.cn) | 1998年 / Atomic Energy Press卷 / 47期
关键词：
Average power; Natural circulation; Nuclear thermal coupling; Rolling motion;
D O I：
10.7538/yzk.2013.47.11.1998
中图分类号：
学科分类号：
摘要：
By performing simulation computations of single-phase flow natural circulation considering nuclear thermal coupling under rolling motion conditions, the influence factors which have great effect on the average heating power of this circulation system were studied. The analysis results indicate that under rolling motion conditions, the average heating power which considers the nuclear thermal coupling effect is in direct proportion to the average flow rate and average heat transfer coefficient, while it has an inverse relationship with the ratio between temperature-feedback coefficient of moderator and that of fuel. The effect of rolling parameters on the average heating power is related with the ratio between temperature-feedback coefficient of moderator and that of fuel. When the effect of the variation of the average heat transfer coefficient on the reactivity plays a leading role in the process, the stronger the rolling motion is, the higher the average heating power is. However, when the effect of the variation for the average friction coefficient on the reactivity takes the lead, the stronger the rolling motion is, the lower the average heating power is.
引用
收藏
页码：1998 / 2002
页数：4
相关论文
共 10 条
  • [1] Wang F., Nie C., Huang Y., Et al., Experimental investigation on nature circulation static characteristics, Chinese Journal of Nuclear Science and Engineering, 24, 2, pp. 134-138, (2004)
  • [2] Tan S., Gao P., Su G., Experimental and theoretical study on natural circulation flow under rolling motion condition, Journal of Harbin Engineering University, 28, 11, pp. 1213-1217, (2007)
  • [3] Murata H., Sawada K., Kobayashi M., Natural circulation characteristics of a marine reactor in rolling motion and heat transfer in the core, Nuclear Engineering and Design, 215, 1-2, pp. 69-85, (2002)
  • [4] Gao P., Pang F., Wang Z.-X., Mathematical model of primary coolant in nuclear power plant influenced by ocean conditions, Journal of Harbin Engineering University, 18, 1, pp. 24-27, (1997)
  • [5] Tan S., Pang F., Gao P., Experimental research of effect of rolling upon heat transfer characteristic of natural circulation, Nuclear Power Engineering, 27, 5, pp. 33-36, (2006)
  • [6] Tan S., Su G., Experimental and theoretical study on single-phase natural circulation flow and heat transfer under rolling motion condition, Applied Thermal Engineering, 29, 14-15, pp. 3160-3168, (2009)
  • [7] Yu L., Cai Z., Development of spatio-temporal neutron kinetics simulation software for marine nuclear reactor core, Journal of Naval University of Engineering, 16, 1, pp. 54-58, (2004)
  • [8] Yang J., Jia B., Yu J., Simulation model of natural circulation in PWR coolant system under ocean conditions, Chinese Journal of Nuclear Science and Engineering, 22, 2, pp. 125-129, (2002)
  • [9] (2004)
  • [10] (2000)
1