VOID FRACTION IN SIMULATED BWR FUEL ASSEMBLY .1. SPACER EFFECT ON VOID FRACTION AND ANALYSIS WITHOUT CROSS-FLOW

被引:2
|
作者
MOROOKA, S
SHIRAKAWA, K
ISHIZUKA, T
YOSHIMURA, K
MAWATARI, K
机构
来源
关键词
2 PHASE FLOW; VOID FRACTION; X-RAY CT SCANNER; FLOW PATTERN; MEASUREMENT; EXPERIMENTAL DATA; STEAM; WATER; ROD BUNDLE; BWR TYPE REACTORS; SPACER; SUBCHANNEL ANALYSIS;
D O I
10.3327/jaesj.33.585
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
Void measurement of a vertical 4 x 4 rod bundle has been conducted behind a spacer in a steam-water two-phase flow using an advanced X-ray CT scanner and one-dimensional single subchannel analysis without a cross-flow was done. It was found from the experimental results that the cross-sectional averaged void fraction data behind the spacer could be predicted by the drift-flux model, that the spacer has a negligible effect on the cross-sectional averaged void fraction and that EPRI correlation made it possible to accurately predict the void data. In addition, the simplified single subchannel analysis without the cross-flow between subchannels gave good agreement with data of center subchannels in a quality range of 5% or more. However, the analysis predicted higher void fraction than experimental results in the corner subchannel.
引用
收藏
页码:585 / 593
页数:9
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