DNB PREDICTION METHOD USING LOCAL VOID DISTRIBUTION IN ROD-BUNDLE

被引:0
|
作者
Sasakawa, Tatsuya [1 ]
Ikeno, Tsutomu [1 ]
Kataoka, Isao [2 ]
机构
[1] Nucl Fuel Ind Ltd, Kumatori, Osaka, Japan
[2] Osaka Univ, Suita, Osaka, Japan
关键词
CRITICAL HEAT-FLUX;
D O I
暂无
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
A computational multi-fluid dynamics (CMFD) code that predicted the void distribution in sub-channel was coupled with sub-channel analysis code to predict departure from nucleate boiling (DNB). The main assumption was that the void fraction near heated wall was the dominant parameter in DNB. A sub-channel analysis code was used to calculate three dimensional distribution of sub-channel averaged values of mass flux, void fraction, density and quality. These were used as a boundary condition in the CMFD code to predict local void fraction in a subchannel. A bubble diffusion equation was used assuming the wall peak void distribution caused by turbulence. The present method was applied to the analysis of DNB tests. The coupled codes showed a reasonable profile of void fraction in a rod bundle and reproduced DNB heat flux at low void fraction. To investigate this analysis result, the local condition were compared with a DNB flow regime map. This suggested an approach to improve the predictability: the critical void fraction should be modified at low void fraction condition; the bubble diffusion model should be modified to handle the flow regime transition from the isolated nucleation type to churn turbulent flow type.
引用
收藏
页码:349 / +
页数:2
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