Power transient critical heat flux in a narrow rectangular channel under downward flow

被引:2
|
作者
Kim, Huiyung [1 ,2 ]
Moon, Jeongmin [2 ]
Kim, Taeho [2 ]
Jeong, Jae Jun [2 ]
Yun, Byongjo [2 ]
机构
[1] Korea Atom Energy Res Inst, 111,Daedeok-daero 989beon-gil, Daejeon 34057, South Korea
[2] Pusan Natl Univ, Sch Mech Engn, Pusan 46241, South Korea
基金
新加坡国家研究基金会;
关键词
Power transient CHF; Narrow rectangular channel; Downward flow; Plate-type fuel; Research reactor; POOL;
D O I
10.1016/j.nucengdes.2021.111587
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
Power transient critical heat flux (CHF) experiments were conducted under downward flow conditions in a narrow rectangular channel simulating a sub-channel consisting of plate-type fuels for a research reactor. The test section is designed as a sub-channel with a wetted width of 66.6 mm, heated width of 62 mm, gap size of 2.35 mm, and length of 640 mm. In the experiment, a mass flux of 3750 kg/m(2)s with a downward flow, an inlet temperature of 37 ?, and outlet pressure of 170 kPa were maintained constantly at a given heat flux transient condition. The heat flux was exponentially increased with the power increase rate ranging from 0.03 to 1 s(-1) for the simulation of power transients in the reactivity-initiated accidents of the research reactor. It was found that the CHF increased significantly as the power increase rate increased at a given flow condition. The power transient CHF was analyzed using a dimensionless velocity consisting of parameters representing the liquid-sublayer thinning mechanism that is expected in the vicinity of the heated wall. Finally, we developed a power transient CHF correlation based on the experimental data set consisting of the present data, data of Kataoka et al., and the R-12 data of Celata et al. The developed correlations showed an average error of 0.24% and root mean square error of 3.09% against the experimental data set for power increase rates of 0.03-1 s(-1).
引用
收藏
页数:12
相关论文
共 50 条
  • [21] Experimental study on flow instability for downward flow in a narrow rectangular channel with flow pattern transition
    Zhang, Xue
    Feng, Wenpei
    Zhang, Jie
    Guo, Simao
    Ding, Wenjie
    Chen, Hongli
    INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, 2020, 114
  • [22] FORCED LIQUID-HELIUM FLOW TRANSIENT HEAT-TRANSFER IN A NARROW CHANNEL UNDER STEP HEAT-FLUX
    YARMAK, IL
    ZHUKOV, VM
    CRYOGENICS, 1992, 32 (08) : 729 - 736
  • [23] Study on the subcooled boiling pressure drop for downward flow in a narrow rectangular channel
    Zhang, Xue
    Feng, Wenpei
    Zhang, Jie
    Chen, Hongli
    ANNALS OF NUCLEAR ENERGY, 2021, 154
  • [24] THEORETICAL CALCULATION OF THE CRITICAL HEAT FLUX IN ANNULAR UPWARD FLOW IN VERTICAL NARROW RECTANGULAR CHANNELS
    Du, Dongxiao
    Su, Guanghui
    Qiu, Suizheng
    ICONE17, VOL 4, 2009, : 311 - 319
  • [25] Influence of tube diameter on critical heat flux in downward flow
    Ami, Takeyuki
    Harada, Takayuki
    Umekawa, Hisashi
    Ozawa, Mamoru
    Multiphase Science and Technology, 2015, 27 (01) : 77 - 97
  • [26] CRITICAL HEAT FLUX DURING SUBCOOLED FLOW BOILING OF ALUNIMNA NANOFLUIDS IN A NARROW CHANNEL
    Vafaei, Saeid
    Wen, Dongsheng
    PROCEEDINGS OF THE ASME INTERNATIONAL HEAT TRANSFER CONFERENCE - 2010, VOL 1: BIO HEAT TRANSFER, BOILING HEAT TRANSFER, COMPUTATIONAL HEAT TRANSFER, 2010, : 215 - 219
  • [27] Flow Instability in Parallel Narrow Rectangular Channel under Different Radial Heat Distribution
    Wang, Yanlin
    Zhou, Lei
    Zan, Yuanfeng
    Yang, Zumao
    Yan, Xiao
    Hedongli Gongcheng/Nuclear Power Engineering, 2021, 42 (02): : 65 - 68
  • [28] Study on flow and heat transfer characteristics of liquid metal flow in narrow rectangular channels under high heat flux
    Zhang, Xue
    Feng, Wenpei
    Yu, Hongxing
    Deng, Jian
    Du, Sijia
    Wang, Xiaoyu
    FRONTIERS IN ENERGY RESEARCH, 2024, 12
  • [29] EXPERIMENTAL INVESTIGATION OF CONVECTIVE HEAT TRANSFER IN A NARROW RECTANGULAR CHANNEL FOR UPWARD AND DOWNWARD FLOWS
    Jo, Daeseong
    Al-Yahia, Omar S.
    Altamimi, Raga'i M.
    Park, Jonghark
    Chae, Heetaek
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2014, 46 (02) : 195 - 206
  • [30] Flow Instability (FI) for subcooled flow boiling through a narrow rectangular channel under transversely uniform and non-uniform heat flux
    Al-Yahia, Omar S.
    Kim, Taewoo
    Jo, Daeseong
    INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2018, 125 : 116 - 128