Research on void drift between rod bundle subchannels

被引:0
作者
Liu, Shasha [1 ,2 ]
Ma, Zaiyong [1 ,2 ]
Pang, Bo [3 ]
Zhang, Rui [1 ,2 ]
Zhang, Luteng [1 ,2 ]
Ren, Quanyao [4 ]
Pan, Liangming [1 ,2 ]
机构
[1] Chongqing Univ, Key Lab Low Grade Energy Utilizat Technol & Syst, Minist Educ, Chongqing 400044, Peoples R China
[2] Chongqing Univ, Dept Nucl Engn & Nucl Technol, Chongqing 400044, Peoples R China
[3] Shenzhen Univ, Dept Nucl Sci & Technol, Shenzhen 518060, Peoples R China
[4] Sci & Technol Reactor Syst Design Technol Lab, Chengdu 610041, Peoples R China
基金
中国国家自然科学基金;
关键词
Rod bundle subchannels; Void drift; Void fraction; Flow regime; FLOW REDISTRIBUTION; 2-PHASE; PREDICTION; CHANNEL;
D O I
10.1016/j.net.2024.03.033
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 drift between subchannels in a rod bundle is a crucial phenomenon affecting the calculation accuracy of thermal-hydraulic parameters in SMRs. It holds significant importance in enhancing the precision of safety analysis for SMRs. Existing research on experiment and model of void drift between rod bundle subchannels is relatively rare, and the accuracy of model calculations requires improvement. In this study, experiments on gasliquid two-phase non-equilibrium flow were conducted to measure the redistribution of two-phase flow induced by void drift in a 1 x 2 rod bundle. The experiment results indicated that in bubby flow regime with void fraction less than 0.3, the void diffusion coefficient showed little variation with changes in void fraction. However, in slug flow and annular flow regimes with void fraction exceeding 0.3, the void diffusion coefficient significantly increased with an increase in void fraction. Furthermore, a new void drift model was developed and validated based on a subchannel code. The overall predicted uncertainty for the outlet void fraction in the rod bundle benchmark was less than 13%.
引用
收藏
页码:3330 / 3334
页数:5
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