Numerical Study on Dryout Critical Boiling in Vertical Circular Tube under Rolling Conditions

Qi Wei; Bu Shanshan; Li Zhenzhong; Ma Zaiyong; Zhang Luteng; Chen Deqi

doi:10.13832/j.jnpe.2022.05.0063

Volume 43 Issue 5

Oct. 2022

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2022 > 43(5): 63-69

Qi Wei, Bu Shanshan, Li Zhenzhong, Ma Zaiyong, Zhang Luteng, Chen Deqi. Numerical Study on Dryout Critical Boiling in Vertical Circular Tube under Rolling Conditions[J]. Nuclear Power Engineering, 2022, 43(5): 63-69. doi: 10.13832/j.jnpe.2022.05.0063

Citation:

Qi Wei, Bu Shanshan, Li Zhenzhong, Ma Zaiyong, Zhang Luteng, Chen Deqi. Numerical Study on Dryout Critical Boiling in Vertical Circular Tube under Rolling Conditions[J]. Nuclear Power Engineering, 2022, 43(5): 63-69. doi: 10.13832/j.jnpe.2022.05.0063

Citation:

PDF( 5985 KB)

Numerical Study on Dryout Critical Boiling in Vertical Circular Tube under Rolling Conditions

doi: 10.13832/j.jnpe.2022.05.0063

Key Laboratory of Low-Grade Energy Utilization Technologies & System, Chongqing University, Chongqing, 400044, China

Received Date: 2021-10-22
Rev Recd Date: 2021-12-16
Publish Date: 2022-10-12

Abstract

Abstract

The three-dimensional numerical calculation of the dryout critical heat flux (Dryout CHF) in a circular tube under rolling conditions is carried out. The phase distribution characteristics, the location of critical heat flux (CHF) and the maximum wall temperature in the circular tube under rolling condition are studied, and the characteristics of heat transfer coefficient along the tube wall are analyzed. The results show that under the rolling condition, the phase distribution in the circular tube changes periodically, and the position of CHF also changes periodically; At the same time, it is found that the rolling motion leads to a higher maximum wall temperature, so the rolling condition will make the boiling critical phenomenon more serious. With the change of flow pattern and boiling heat transfer mechanism, the wall heat transfer coefficient will also change significantly along the flow direction. This study can provide a reference for the numerical prediction of dryout CHF under rolling condition.
- Dryout CHF,
- Rolling conditions,
- Wall temperature,
- Heat transfer coefficient

FullText(HTML)

References(15)

References

[1]	高璞珍,王兆祥,庞凤阁,等. 摇摆情况下水的自然循环临界热流密度实验研究[J]. 哈尔滨工程大学学报,1997, 18(6): 38-42.
[2]	HWANG J S, LEE Y G, PARK G C. Characteristics of critical heat flux under rolling condition for flow boiling in vertical tube[J]. Nuclear Engineering and Design, 2012, 252: 153-162. doi: 10.1016/j.nucengdes.2012.06.032
[3]	TANJUNG E F, JO D. Visualization study on pool boiling critical heat flux under rolling motion[J]. International Journal of Heat and Mass Transfer, 2020, 153: 119620. doi: 10.1016/j.ijheatmasstransfer.2020.119620
[4]	徐海淞. 基于拉格朗日—欧拉法的环状流模拟及干涸型临界热流密度预测研究[D]. 上海: 上海交通大学, 2019.
[5]	陈丽娟. 竖直加热管道内干涸型临界沸腾数值分析[D]. 哈尔滨: 哈尔滨工程大学, 2018.
[6]	DU D X, TIAN W X, SU G H, et al. Theoretical study on the characteristics of critical heat flux in vertical narrow rectangular channels[J]. Applied Thermal Engineering, 2012, 36: 21-31. doi: 10.1016/j.applthermaleng.2011.11.039
[7]	GUI M Y, TIAN W X, WU D, et al. Development of a three-field mechanistic model for dryout prediction in annular flow[J]. Annals of Nuclear Energy, 2020, 135: 106978. doi: 10.1016/j.anucene.2019.106978
[8]	GUI M Y, TIAN W X, WU D, et al. Study on CHF characteristics in narrow rectangular channel under complex motion condition[J]. Applied Thermal Engineering, 2020, 166: 114629. doi: 10.1016/j.applthermaleng.2019.114629
[9]	桂民洋,田文喜,吴迪,等. 棒束子通道CHF机理模型开发及初步验证[J]. 原子能科学技术,2021, 55(11): 1930-1938. doi: 10.7538/yzk.2021.youxian.0046
[10]	PENG J, CHEN D Q, XU J J, et al. CFD simulation focusing on void distribution of subcooled flow boiling in circular tube under rolling condition[J]. International Journal of Heat and Mass Transfer, 2020, 156: 119790. doi: 10.1016/j.ijheatmasstransfer.2020.119790
[11]	TENTNER A, LO S, IOILEV A, et al. Computational fluid dynamics modeling of two-phase flow topologies in a boiling water reactor fuel assembly[C]//Proceedings of the 16th International Conference on Nuclear Engineering. Orlando: ASME, 2008: 178-183.
[12]	RANZ W E, MARSHALL W R. Evaporation from drops[J]. Chemical Engineering Progress, 1952, 48(3): 141-146.
[13]	魏列. 运动条件对自然循环系统驱动力特性的影响机制研究[D]. 重庆: 重庆大学, 2020.
[14]	BECKER K M, LING C H, HEDBERG S, et al. An experimental investigation of post dryout heat transfer[R]. Stockholm: Department of Nuclear Reactor Engineering Royal Institute of Technology Stockholm, 1983.
[15]	史建新. 直管式直流蒸汽发生器蒸干及蒸干后传热数值模拟[D]. 哈尔滨: 哈尔滨工程大学, 2019.