Numerical simulation using CFD software of countercurrent gas-liquid flow in a PWR hot leg under reflux condensation

被引:12
|
作者
Utanohara, Yoichi [1 ]
Kinoshita, Ikuo [1 ]
Murase, Michio [1 ]
Minami, Noritoshi [2 ]
Nariai, Toshifumi [3 ]
Tomiyama, Akio [3 ]
机构
[1] Inst Nucl Safety Syst Inc, Mihama, Fukui 9191205, Japan
[2] Kansai Elect Power Co Inc, Mihama, Fukui 9191141, Japan
[3] Kobe Univ, Grad Sch Engn, Nada Ku, Kobe, Hyogo 6578501, Japan
关键词
AIR-WATER TESTS; INCLINED RISER; 2-PHASE FLOW; MODEL;
D O I
10.1016/j.nucengdes.2011.01.051
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 order to improve the countercurrent flow model of a transient analysis code, countercurrent air-water tests were previously conducted using a 1/15 scale model of the PWR hot leg and numerical simulations of the tests were carried out using the two-Fluid model implemented in the CFD software FLUENT 6.3.26. The predicted flow patterns and CCFL characteristics agreed well with the experimental data. However, the validation of the interfacial drag correlation used in the two-fluid model was still insufficient, especially regarding the applicability to actual PWR conditions. In this study, we measured water levels and wave heights in the 1/15 scale setup to understand the characteristics of the interfacial drag, and we considered a relationship between the wave height and the interfacial drag coefficient. Numerical simulations to examine the effects of cell size and interfacial drag correlations on numerical predictions were conducted under PWR plant conditions. Wave heights strongly related with the water level and interfacial drag coefficient, which indicates that the interfacial drag force mainly consists of form drag. The cell size affected the gas velocity at the onset of flooding in the process of increasing gas flow rate. The gas volumetric fluxes at CCFL predicted using fine cells were higher than those using normal cells. On the other hand, the cell size did not have a significant influence on the process of decreasing gas flow rate. The predictions for the PWR condition using a reference set of interfacial drag correlations agreed well with the Upper Plenum Test Facility data of the PWR scale experiment in the region of medium gas volumetric fluxes. The reference interfacial drag correlations employed in this study can be applied to the PWR conditions. (C) 2011 Elsevier B.V. All rights reserved.
引用
收藏
页码:1643 / 1655
页数:13
相关论文
共 46 条
  • [1] Numerical Simulation of Countercurrent Gas-Liquid Flow in a PWR Hot Leg under Reflux Cooling
    Kinoshita, Ikuo
    Murase, Michio
    Utanohara, Yoichi
    Minami, Noritoshi
    Tomiyama, Akio
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2010, 47 (10) : 963 - 972
  • [2] VOF Calculations of Countercurrent Gas-Liquid Flow in a PWR Hot Leg
    Murase, M.
    Tomiyama, A.
    Kinoshita, I.
    Utanohara, Y.
    Yanagi, Chihiro
    Takata, T.
    Yamaguchi, A.
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2012, 2012
  • [3] Countercurrent Gas-Liquid Flow in a PWR Hot Leg under Reflux Cooling (II) Numerical Simulation of 1/15-Scale Air-Water Tests
    Minami, Noritoshi
    Murase, Michio
    Tomiyama, Akio
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2010, 47 (02) : 149 - 155
  • [4] STUDY ON COUNTERCURRENT FLOW IN A PWR HOT LEG UNDER REFLUX COOLING
    Minami, Noritoshi
    Murase, Michio
    Tomiyama, Akio
    PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 4 PTS A AND B, 2011, : 963 - +
  • [5] Gas-liquid countercurrent two-phase flow in a PWR hot leg: A comprehensive research review
    Deendarlianto
    Hoehne, Thomas
    Lucas, Dirk
    Vierow, Karen
    NUCLEAR ENGINEERING AND DESIGN, 2012, 243 : 214 - 233
  • [6] Numerical Simulation of Size Effects on Countercurrent Flow Limitation in PWR Hot Leg Models
    Kinoshita, I.
    Murase, M.
    Tomiyama, A.
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2012, 2012
  • [7] DEVELOPMENT OF INTERFACIAL FRICTION MODEL FOR 2-FLUID MODEL CODE AGAINST COUNTERCURRENT GAS-LIQUID FLOW LIMITATION IN PWR HOT LEG
    OHNUKI, A
    AKIMOTO, H
    MURAO, Y
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1992, 29 (03) : 223 - 232
  • [8] CFD studies on the phenomena around counter-current flow limitations of gas/liquid two-phase flow in a model of a PWR hot leg
    Deendarlianto
    Hoehne, Thomas
    Lucas, Dirk
    Vallee, Christophe
    Zabala, Gustavo Adolfo Montoya
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (12) : 5138 - 5148
  • [9] Experimental investigation and CFD validation of countercurrent flow limitation (CCFL) in a large-diameter PWR hot-leg geometry
    Al Issa, Suleiman
    Macian-Juan, Rafael
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2016, 53 (05) : 647 - 655
  • [10] NUMERICAL CALCULATIONS ON COUNTERCURRENT AIR-WATER FLOW IN SMALL-SCALE MODELS OF A PWR HOT LEG USING A VOF MODEL
    Murase, Michio
    Utanohara, Yoichi
    Kinoshita, Ikuo
    Minami, Noritoshi
    Tomiyama, Akio
    ICONE 17: PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 3, 2009, : 141 - 148