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
相关论文
共 50 条
  • [31] Numerical simulation of transient boiling and void cross flow in non-uniformly heated 5 x 5 rod bundle
    Okawa, Riichiro
    Furuya, Masahiro
    Arai, Takahiro
    Iiyama, Tsugumasa
    Shirakawa, Kenetsu
    NUCLEAR ENGINEERING AND DESIGN, 2024, 416
  • [32] Subchannel void-fraction measurements in a 6 x 6 rod bundle using a simple gamma-transmission method
    Kok, HV
    van der Hagen, THJJ
    Mudde, RF
    INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 2001, 27 (01) : 147 - 170
  • [33] One-dimensional drift-flux model for two-phase flow in pool rod bundle systems
    Chen, Shao-Wen
    Liu, Yang
    Hibiki, Takashi
    Ishii, Mamoru
    Yoshida, Yoshitaka
    Kinoshita, Ikuo
    Murase, Michio
    Mishima, Kaichiro
    INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 2012, 40 : 166 - 177
  • [34] A Review of Void Drift Models in Subchannel Analysis
    Mao, Hu
    Yang, Bao-Wen
    Wang, Sipeng
    NUCLEAR SCIENCE AND ENGINEERING, 2019, 193 (1-2) : 33 - 45
  • [35] Void fraction measurements of steam-water two-phase flow in vertical rod bundle: Comparison among different techniques
    Gui, Miao
    Liu, Zhaohui
    Liao, Bo
    Wang, Teng
    Wang, Yong
    Sui, Zhiqiang
    Bi, Qincheng
    Wang, Jun
    EXPERIMENTAL THERMAL AND FLUID SCIENCE, 2019, 109
  • [36] An experimental research of the influence on critical heat flux of a rod bundle under certain inlet temperatures
    Duan, Minghui
    Zhao, Minfu
    Wei, Junhan
    Xu, Yongwang
    FRONTIERS IN ENERGY RESEARCH, 2024, 12
  • [37] Drift-flux correlation for upward gas-liquid two-phase flow in vertical rod bundle flow channel
    Han, Xu
    Shen, Xiuzhong
    Yamamoto, Toshihiro
    Nakajima, Ken
    Hibiki, Takashi
    INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2020, 162
  • [38] Direct Numerical Simulation of the Flow in a Bare Rod Bundle at Different Prandtl Numbers
    Lai, Jonathan K.
    Busco, Giacomo
    Merzari, Elia
    Hassan, Yassin A.
    JOURNAL OF HEAT TRANSFER-TRANSACTIONS OF THE ASME, 2019, 141 (12):
  • [39] Research on the relationship between sound velocity and void fraction in bubbly flow
    Zheng, Dandan
    Li, Fengxian
    Wang, Maosen
    2024 IEEE INTERNATIONAL INSTRUMENTATION AND MEASUREMENT TECHNOLOGY CONFERENCE, I2MTC 2024, 2024,
  • [40] Critical Power and Void Fraction Prediction of Tight Bundle Designs
    Zhao, Xingang
    Shirvan, Koroush
    Wu, Yingwei
    Kazimi, Mujid S.
    NUCLEAR TECHNOLOGY, 2016, 196 (03) : 553 - 567