Transient boiling flow in 5 x 5 rod bundle under non-uniform rapid heating

被引:10
作者
Takiguchi, Hiroki [1 ]
Furuya, Masahiro [1 ]
Arai, Takahiro [1 ]
Shirakawa, Kenetsu [1 ]
机构
[1] Cent Res Inst Elect Power Ind, 2-6-1 Nagasaka, Yokosuka, Kanagawa 2400196, Japan
关键词
Transient boiling; Rapid heating; Cross vapor propagation; 5 x 5 rod bundle; BWR fuel; Wire mesh sensor; INPUTS; WATER;
D O I
10.1016/j.nucengdes.2018.10.018
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
Rapid thermal elevation in boiling water reactor (BWR) is an important factor for nuclear safety and there is a need to develop an analysis code for the transient phenomenon and its validation process. To evaluate the thermal property of transient boiling and its uncertainty, corroborative experimental information is crucial. In particular, the lateral propagation behavior of a vapor bubble (void) in the cross-sectional direction of fuel assembly has yet to be determined. This study evaluates the void propagation behavior in a 5 x 5 rod bundle with cross-sectional heat distribution that causes only the 3 x 3 rod bundle to generate heat; assuming rapid heating under atmospheric pressure. In this paper, using the maximum heat output applied to the nine heated rods as a parameter, from the visualization of the void behavior and the measurement of the local void fraction, the heat output conditions under circumstances where lateral propagation of voids occurs and where voids are only localized in the heated region are summarized. We quantified the time difference initially detected and the time-averaged void fraction according to the lateral propagation level.
引用
收藏
页码:447 / 456
页数:10
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