Power transient critical heat flux in a narrow rectangular channel under downward flow

被引:2
|
作者
Kim, Huiyung [1 ,2 ]
Moon, Jeongmin [2 ]
Kim, Taeho [2 ]
Jeong, Jae Jun [2 ]
Yun, Byongjo [2 ]
机构
[1] Korea Atom Energy Res Inst, 111,Daedeok-daero 989beon-gil, Daejeon 34057, South Korea
[2] Pusan Natl Univ, Sch Mech Engn, Pusan 46241, South Korea
基金
新加坡国家研究基金会;
关键词
Power transient CHF; Narrow rectangular channel; Downward flow; Plate-type fuel; Research reactor; POOL;
D O I
10.1016/j.nucengdes.2021.111587
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
Power transient critical heat flux (CHF) experiments were conducted under downward flow conditions in a narrow rectangular channel simulating a sub-channel consisting of plate-type fuels for a research reactor. The test section is designed as a sub-channel with a wetted width of 66.6 mm, heated width of 62 mm, gap size of 2.35 mm, and length of 640 mm. In the experiment, a mass flux of 3750 kg/m(2)s with a downward flow, an inlet temperature of 37 ?, and outlet pressure of 170 kPa were maintained constantly at a given heat flux transient condition. The heat flux was exponentially increased with the power increase rate ranging from 0.03 to 1 s(-1) for the simulation of power transients in the reactivity-initiated accidents of the research reactor. It was found that the CHF increased significantly as the power increase rate increased at a given flow condition. The power transient CHF was analyzed using a dimensionless velocity consisting of parameters representing the liquid-sublayer thinning mechanism that is expected in the vicinity of the heated wall. Finally, we developed a power transient CHF correlation based on the experimental data set consisting of the present data, data of Kataoka et al., and the R-12 data of Celata et al. The developed correlations showed an average error of 0.24% and root mean square error of 3.09% against the experimental data set for power increase rates of 0.03-1 s(-1).
引用
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页数:12
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