Experimentally investigating boiling characteristics in the transition boiling for the downward facing heating

被引:2
|
作者
Chuang, T. J. [1 ]
Ferng, Y. M. [1 ]
机构
[1] Natl Tsing Hua Univ, Dept Engn & Syst Sci, Inst Nucl Engn & Sci, 101,Sect 2,Kuang Fu Rd, Hsingchu 30013, Taiwan
关键词
Downward facing heating; CHF; Transition boiling; Leidenfrost temperature; SURFACE; CHF;
D O I
10.1016/j.anucene.2016.01.004
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
The external reactor vessel cooling (ERVC) can retain the molten corium to ensure the vessel remains intact via boiling heat transfer on the outer wall of the vessel. This downward facing heating layout research attracts much attention for nuclear safety. The heat removal capability for the boiling heat transfer is limited to the CHF value and the rewet of overheated vessel wall is determined by the Leidenfrost temperature. This paper investigates the heat transfer characteristics and bubble dynamics of transition boiling regime for the downward facing heating by way of experimental measurements and observation. Effects of injection flow rate and, gap distance are considered. The CHF can be elevated as the injection flow rate increases or the gap distance is reduced. The Leidenfrost temperature would increase with decreasing the gap distance. The measured data reveal that nucleate boiling/transition boiling/nucleate boiling cycles exist in the transition boiling region of the boiling curve. These cycling and data fluctuation characteristics increase with the higher injection flow rate or the smaller gap distance. In addition, based on the experimental observations, the bubble size stuck on the heating surface during the transition boiling regime is smaller for the higher injection flow rate due to condensation and flow disturbance. (C) 2016 Elsevier Ltd. All rights reserved.
引用
收藏
页码:148 / 155
页数:8
相关论文
共 50 条
  • [41] An experimental investigation of subcooled pool boiling on downward-facing surfaces with microchannels
    Gao, Zhijie
    Hong, Sihui
    Dang, Chaobin
    APPLIED THERMAL ENGINEERING, 2023, 226
  • [42] CHARACTERISTICS OF TRANSITION BOILING AND THERMAL OSCILLATION IN AN UPFLOW CONVECTIVE BOILING SYSTEM
    LIU, HT
    KAKAC, S
    MAYINGER, F
    EXPERIMENTAL THERMAL AND FLUID SCIENCE, 1994, 8 (03) : 195 - 205
  • [43] Flow boiling heat transfer and pressure fluctuation characteristics in a divergent channel with inclined downward-facing heater
    Dong, Shichang
    Jin, Yu
    Gong, Shengjie
    Wu, Yikai
    Li, Wei
    Guo, Qiang
    Xiong, Zhenqin
    Yuan, Yidan
    APPLIED THERMAL ENGINEERING, 2024, 240
  • [44] Boiling in nanopores through localized Joule heating: Transition between nucleate and film boiling
    Paul, Soumyadeep
    Hsu, Wei-Lun
    Ito, Yusuke
    Daiguji, Hirofumi
    PHYSICAL REVIEW RESEARCH, 2022, 4 (04):
  • [45] A Study on Boiling Heat Transfer Performance of TiO2-CNTs Hybrid Nanofluid on a Downward-Facing Heating Surface
    Liu, Songling
    Hsieh, Huai-En
    Wang, Shiqi
    NUCLEAR TECHNOLOGY, 2025, 211 (02) : 200 - 213
  • [46] Critical heat flux for downward-facing pool boiling on CANDU calandria vessel
    Behdadi, Azin
    Talebi, Farshad
    Luxat, John
    ANNALS OF NUCLEAR ENERGY, 2017, 110 : 768 - 778
  • [47] OPTIMAL GAP SIZE FOR DOWNWARD FACING BOILING AND STEAM VENTING IN A HEMISPHERICAL ANNULAR CHANNEL
    Narayanan, Shankar
    Cheung, Fan-Bill
    Hochreiter, Lawrence
    NUCLEAR TECHNOLOGY, 2009, 167 (01) : 178 - 186
  • [48] Investigation of the Crisis of Heat Transfer under Conditions of Boiling on an Inclined Surface Facing Downward
    A. A. Sulatskii
    O. D. Chernyi
    V. K. Efimov
    High Temperature, 2002, 40 : 912 - 918
  • [49] Experimental Study of Flow Boiling Heat Transfer on a Downward-Facing Heated Wall
    Kwon, Soonil
    Park, Sang Min
    Jin, Taehyeong
    Kim, Hyungdae
    TRANSACTIONS OF THE KOREAN SOCIETY OF MECHANICAL ENGINEERS B, 2020, 44 (09) : 547 - 556
  • [50] Azimuthal film-boiling heat transfer from a downward-facing hemisphere
    Yu, Mong J.
    Kim, Chan S.
    Suh, Kune Y.
    NUCLEAR TECHNOLOGY, 2007, 157 (03) : 261 - 276