Investigation on Heat Transfer Characteristics of Liquid Lead-bismuth Eutectic and Helium in ADS Two-loop Cooling System

被引:0
|
作者
Xi, Wen-Xuan [1 ,2 ]
Cai, Jun [1 ,2 ]
Huai, Xiu-Lan [1 ,2 ]
机构
[1] Institute of Engineering Thermophysics, Chinese Academy of Sciences, Beijing,100190, China
[2] University of the Chinese Academy of Sciences, Beijing,100049, China
关键词
Liquids;
D O I
暂无
中图分类号
学科分类号
摘要
The study on the coupled heat transfer characteristics of liquid lead-bismuth eutectic (LBE) and helium through the experimental and numerical simulation methods is of great significance for the development of the accelerator-driven system (ADS) two-loop cooling system. In this paper, a liquid LBE-helium coupled heat transfer experiment platform was set up, and the experiments of variable mass-flow-rates and variable inlet temperatures were carried out. The influences of different Reynolds number and inlet temperature on the heat transfer were investigated. At the same time, a 3D full scale numerical model of the main heat exchanger (MHX) in the experiment platform was constructed and a large number of numerical simulations were carried out. The present model is verified by comparing the numerical results with experimental results. On the base of model validation, the distributions of velocity field and temperature field of liquid LBE and helium in the MHX were further studied based on the field synergy principle. The coupled heat transfer characteristics between liquid LBE and helium in the MHX were analyzed. © 2019, Science Press. All right reserved.
引用
收藏
页码:2094 / 2101
相关论文
共 50 条
  • [21] Comparative Analysis on the Characteristics of Liquid Lead and Lead-Bismuth Eutectic as Coolants for Fast Reactors
    Xing, Mian
    Fan, Jihong
    Shen, Feng
    Lu, Daogang
    Li, Linsen
    Yu, Hui
    Fan, Jin
    ENERGIES, 2025, 18 (03)
  • [22] Investigation on turbulent heat transfer to lead-bismuth eutectic flows in rough rod bundles for nuclear applications
    Wang, Xiaowen
    Liu, Maolong
    Zhang, Rui
    Fu, Junsen
    Cong, Tenglong
    Gu, Hanyang
    INTERNATIONAL JOURNAL OF THERMAL SCIENCES, 2024, 204
  • [23] Numerical study on conjugate heat transfer characteristics of liquid lead-bismuth eutectic and supercritical carbon dioxide in a PCHE straight channel
    Su, Xing-Kang
    Li, Xian-Wen
    Wang, Xiang-Yang
    Chen, Qi-Jian
    Shi, Qian-Wan
    Qiu, Jing
    Gu, Long
    ANNALS OF NUCLEAR ENERGY, 2023, 186
  • [24] Heat transfer evaluation of liquid lead-bismuth eutectic cross flow tube bundle: Experimental part
    Yang, Yupeng
    Wang, Chenglong
    Zhang, Dalin
    Qiu, Suizheng
    Su, Guanghui
    Tian, Wenxi
    INTERNATIONAL JOURNAL OF THERMAL SCIENCES, 2023, 193
  • [25] Eutectic Lead-Bismuth Alloy as a Possible Coolant in the Fusion Reactor Cooling System
    Deryabina, N. A.
    Kuteev, B. V.
    Pashkov, A. Yu.
    Shpanskiy, Yu. S.
    PHYSICS OF ATOMIC NUCLEI, 2024, 87 (SUPPL1) : S202 - S206
  • [26] Investigation on the performance and flow characteristics of a liquid lead-bismuth pump
    Yongchao Zhang
    Can Kang
    Yang Zhu
    Hyoung-Bum Kim
    Journal of Mechanical Science and Technology, 2021, 35 : 2939 - 2947
  • [27] Investigation on the performance and flow characteristics of a liquid lead-bismuth pump
    Zhang, Yongchao
    Kang, Can
    Zhu, Yang
    Kim, Hyoung-Bum
    JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, 2021, 35 (07) : 2939 - 2947
  • [28] Numerical study on the heat transfer characteristics of a microchannel heat exchanger with liquid lead-bismuth eutectic and supercritical CO2 as working fluids
    Liu, Hong
    Zhang, Zhigang
    Du, Haisu
    Cong, Tenglong
    Yang, Shuo
    ANNALS OF NUCLEAR ENERGY, 2023, 192
  • [29] Investigation of the vacuum pump effect of free flowing liquid lead-bismuth eutectic
    Rosseel, K.
    Van Tichelen, K.
    Walsh, S.
    Dierckx, M.
    Schuurmans, P.
    NUCLEAR ENGINEERING AND DESIGN, 2014, 267 : 61 - 70
  • [30] Dissolved oxygen control and monitoring implementation in the liquid lead-bismuth eutectic loop: HELIOS
    Nam, Hyo On
    Lim, Jun
    Han, Dong Yoon
    Hwang, Il Soon
    JOURNAL OF NUCLEAR MATERIALS, 2008, 376 (03) : 381 - 385