Numerical investigation on the CHF model and prediction for the external cooling channel of lower head

被引:0
|
作者
Li Dan [1 ]
Peng Changhong [1 ]
Li Songwei [2 ]
Guo Yun [1 ]
机构
[1] Univ Sci & Technol China, Sch Phys Sci, Hefei 230026, Anhui, Peoples R China
[2] Nucl Power Inst China, State Key Lab Reactor Syst Design Technol, Chengdu 610041, Peoples R China
关键词
Critical heat flux; Bubble nucleation density; Lower head; NUCLEATION SITE DENSITY; CFD; NEPTUNE;
D O I
10.1016/j.anucene.2019.02.036
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
External cooling of the lower head can reduce the possibility of the damage to the pressure vessel in serious accidents. However, when the core melt heats the lower head with a high heat flux subcooled boiling under natural circulation may cause bubble accumulation, which results in the deterioration of heat transfer or even radioactive leakage. This phenomenon is essentially the critical heat flux (CHF) on a curved surface with a downward heating boundary. The estimation of this phenomenon is indispensable for reactor safety design. In this paper, improvement in the nucleation density model exhibits higher resulting calculation performance for CHF with new geometries or working conditions. The CHF values and CHF distribution along the ellipsoidal and spherical structures are obtained, and detailed comparison between these two structures is made. The characteristics of elliptical cooling channel prove completely different from those of spherical structure, which requires more experimental studies. (C) 2019 Elsevier Ltd. All rights reserved.
引用
收藏
页码:232 / 239
页数:8
相关论文
共 50 条
  • [1] Numerical analysis of heat transfer characteristics of external cooling channel of the lower head
    Li, Dan
    Peng, Changhong
    Guo, Yun
    PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 8, 2018,
  • [2] Experimental and numerical investigation of molten corium behavior in lower head under external subcooling and boiling conditions
    Pandazis, P.
    Hollands, T.
    Gaus-Liu, X.
    Miassoedov, A.
    ANNALS OF NUCLEAR ENERGY, 2018, 120 : 888 - 895
  • [3] An experimental and numerical investigation of the effect of cooling channel crossflow on film cooling performance
    Kissel, Harald Peter
    Weigand, Bernhard
    von Wolfersdorf, Jens
    Neumann, Sven Olaf
    Ungewickell, Antje
    PROCEEDINGS OF THE ASME TURBO EXPO 2007, VOL 4, PTS A AND B, 2007, : 147 - 158
  • [4] Theoretical research of CHF in hemispherical narrow gap channel between molten corium and lower head
    Feng, Kun
    Tian, Wen-Xi
    Wu, Ying-Wei
    Su, Guang-Hui
    Qiu, Sui-Zheng
    Yu, Hong-Xing
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2013, 47 (08): : 1311 - 1315
  • [5] A review on the external cooling of the pressure vessel lower head in nuclear power plant
    Hou, Yandong
    Cai, Rui
    Huang, Xianyao
    Zhang, Chao
    Li, Weichao
    Cai, Benan
    Gao, Chuntian
    Xiang, Yan
    NUCLEAR ENGINEERING AND DESIGN, 2023, 410
  • [6] Numerical investigation of the CHF in a vertical round tube and a single rod channel based on the eulerian two-fluid model
    Liu, Wei
    Shang, Zemin
    Yang, Lixin
    Liu, Yu
    Hu, Ying
    Liu, Yang
    PROGRESS IN NUCLEAR ENERGY, 2021, 135
  • [7] Numerical investigation on cooling performance of pulsating flow in a ribbed channel
    Wei Wang
    Yang Gao
    Genwei Wang
    Haiping Tian
    Journal of Mechanical Science and Technology, 2020, 34 : 1765 - 1774
  • [8] Numerical investigation on cooling performance of pulsating flow in a ribbed channel
    Wang, Wei
    Gao, Yang
    Wang, Genwei
    Tian, Haiping
    JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, 2020, 34 (04) : 1765 - 1774
  • [9] Numerical Investigation of Conjugate Heat Transfer in a Straight Cooling Channel
    Chen, S.
    Fukuda, K.
    Barron, R. M.
    Balachandar, R.
    INTERNATIONAL CONFERENCE ON NUMERICAL ANALYSIS AND APPLIED MATHEMATICS ICNAAM 2019, 2020, 2293
  • [10] Numerical investigation of azimuthal heat conduction effects on CHF phenomenon in rod bundle channel
    Dong, Xiaomeng
    Duarte, Juliana P.
    Liu, Dong
    Wang, Jun
    Zhang, Zhijian
    Tian, Zhaofei
    ANNALS OF NUCLEAR ENERGY, 2018, 121 : 203 - 209