Flow structure of subcooled boiling water flow in a subchannel of 3x3 rod bundles

被引:54
|
作者
Yun, Byong-Jo [2 ]
Park, Goon-Cherl [3 ]
Julia, J. Enrique [1 ]
Hibiki, Takashi [4 ]
机构
[1] Univ Jaume 1, Dept Ingn Mecan & Construcc, Castellon de La Plana 12071, Spain
[2] Korea Atom Energy Res Inst, Taejon 305600, South Korea
[3] Seoul Natl Univ, Dept Nucl Engn, Seoul 151742, South Korea
[4] Purdue Univ, Sch Nucl Engn, W Lafayette, IN 47907 USA
关键词
rod bundle; subchannel; subcooled boiling flow; local measurements; drift-flux model; interfacial area concentration;
D O I
10.3327/jnst.45.402
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
In this paper, the interfacial flow structure of subcooled water boiling flow in a subchannel of 3 x 3 rod bundles is presented. The 9 rods are positioned in a quadrangular assembly with a rod diameter of 8.2 mm and a pitch distance of 16.6 mm. Local void fraction, interfacial area concentration, interfacial velocity, Sauter mean diameter, and liquid velocity have been measured using a conductivity probe and a Pilot tube in 20 locations inside one of the subchannels. A total of 53 flow conditions have been considered in the experimental dataset at atmospheric pressure conditions with a mass flow rate, heat flux, inlet temperature, and subcooled temperature ranges of 250-522 kg/m(2) s, 25-185 kW/m(2), 96.6-104.9 degrees C, and 2-11 K, respectively. The dataset has been used to analyze the effect of the heat flux and mass flow rate on the local flow parameters. In addition, the area-averaged data integrated over the whole subchannel have been used to validate some of the distribution parameter and drift velocity constitutive equations and interfacial area concentration correlations most used in the literature.
引用
收藏
页码:402 / 422
页数:21
相关论文
共 50 条
  • [1] CFD INVESTIGATION OF HEAT TRANSFER IN SUPERCRITICAL WATER-COOLED FLOW THROUGH 3x3 FUEL ROD BUNDLES
    Sang, Zhi
    Yao, Yufeng
    ICONE16: PROCEEDING OF THE 16TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2008, VOL 2, 2008, : 171 - 177
  • [2] Experimental research on subcooled boiling heat transfer for natural circulation flow in a vertical 3 x 3 rod bundle
    Tian, Chunping
    Liu, Yiwen
    Meng, Haibo
    Zhu, Zhiqiang
    Wang, Jianjun
    Yan, Changgi
    ANNALS OF NUCLEAR ENERGY, 2020, 135
  • [3] Heat transfer of a bubbly flow in a vertical rod bundle 3X3
    Vorobyev, M. A.
    Kashinsky, O. N.
    ALL-RUSSIAN CONFERENCE XXXIV SIBERIAN THERMOPHYSICAL SEMINAR, DEDICATED TO THE 85TH ANNIVERSARY OF ACADEMICIAN A. K. REBROV, 2018, 1105
  • [4] LOCAL FLOW STRUCTURE OF SUBCOOLED BOILING FLOW OF WATER IN A HEATED ANNULUS
    Lee, Tae-Ho
    Yun, Byong-Jo
    Park, Goon-Cherl
    Hibiki, Takashi
    Kim, Seong-O
    ICONE16: PROCEEDING OF THE 16TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2008, VOL 3, 2008, : 233 - 244
  • [5] Turbulent flow of water in a 3x3 rod bundle - Numerical results from RANS, URANS and LES
    Wang, Han
    Wang, Shunqi
    Lu, Daogang
    PROGRESS IN NUCLEAR ENERGY, 2020, 129
  • [6] Numerical Study of the Effect of the Rolling Motion on the Subcooled Flow Boiling in the Subchannel
    Li, Yaru
    Chi, Xiangyu
    Nan, Zezhao
    Yin, Xuan
    Ren, Xiaohan
    Wang, Naihua
    ENERGIES, 2022, 15 (13)
  • [7] CFD Analysis of Subcooled Flow Boiling in 4 x 4 Rod Bundle
    Seo, Ye-Bon
    Paramanantham, SalaiSargunan S.
    Bak, Jin-Yeong
    Yun, Byongjo
    Park, Warn-Gyu
    APPLIED SCIENCES-BASEL, 2020, 10 (13):
  • [8] INVESTIGATION OF THE STRUCTURE VELOCITY IN A 3X3 ROD BUNDLE UNDER BUBBLY AND CAP-BUBBLY FLOW REGIMES
    Ruan, Pei-Syuan
    Chen, Shao-Wen
    Lin, Min-Song
    Lee, Jin-Der
    Wang, Jong-Rong
    PROCEEDINGS OF THE 2020 INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE2020), VOL 3, 2020,
  • [9] CFD simulation of subcooled boiling flow in PWR 5 x 5 rod bundle
    Ren, B.
    Dang, Y.
    Gan, F. J.
    Yang, P.
    KERNTECHNIK, 2021, 86 (01) : 24 - 32
  • [10] Vibration characteristic of heated rod induced by subcooled flow boiling
    Nematollahi, MR
    Toda, S
    Hashizume, H
    Yuki, K
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1999, 36 (07) : 575 - 583