Countercurrent flow limitation in a pressurizer surge line

被引:5
|
作者
Yamamoto, Yasunori [1 ,3 ]
Murase, Michio [1 ]
Tomiyama, Akio [2 ]
机构
[1] Inst Nucl Safety Syst Inc, 64 Sata, Mihama, Fukui 9191205, Japan
[2] Kobe Univ, Nada Ku, 1-1 Rokkodai, Kobe, Hyogo 6578501, Japan
[3] Hokkaido Univ, Kita Ku, North 13 West 8, Sapporo, Hokkaido 0608628, Japan
关键词
Pressurizer surge line; Countercurrent flow limitation; Vertical pipe; GAS-LIQUID FLOW; AIR-WATER; STEAM;
D O I
10.1016/j.nucengdes.2017.11.008
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 clarify the characteristics of countercurrent flow limitation (CCFL) in a pressurizer surge line, CCFL in a vertical pipe with a large diameter was evaluated using previous experimental data and a one-region model with an existing correlation of interfacial shear stress. The CCFL is defined by the relationship between the gas and liquid volumetric fluxes under a quasi-steady state after onset of flooding. A correlation for CCFL at the sharp-edged upper end of vertical pipes was constructed and it was compared to CCFL in the slightly inclined pipe. The comparison indicated that the liquid volumetric flux at the sharp-edged upper end was lower than that in a slightly inclined pipe when they have a large diameter such for an actual-scale pressurizer surge line. However, it was found that the liquid volumetric flux in integral experiments ( including a slightly inclined pipe, a vertical elbow, and a vertical pipe) was lower than that in slightly inclined pipes and vertical pipes. Considering system characteristics from experimental data for the pressurizer surge line, it was concluded that the Kutateladze parameter should be applied with the slope of m=0.94 and the constant of CK=1.24 +/- 0.1 for the Wallis type CCFL correlation.
引用
收藏
页码:175 / 182
页数:8
相关论文
共 50 条
  • [31] Experimental Study on Pressurizer Surge Line Double-Ended Break of Small Reactor
    小型堆稳压器波动管双端破口试验研究
    2021, Atomic Energy Press (42): : 82 - 86
  • [32] Flooding in the pressurizer surge line of AP600 plant and analyses of APEX data
    Takeuchi, K
    Young, MY
    Gagnon, AF
    NUCLEAR ENGINEERING AND DESIGN, 1999, 192 (01) : 45 - 58
  • [33] THERMAL STRATIFICATION ANALYSIS AND FATIGUE EVALUATION FOR PRESSURIZER SURGE LINE IN NUCLEAR POWER PLANT
    Xu, Xiao
    Liu, Pan
    Zhang, Guihe
    Wang, Dasheng
    jin, Ting
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 2, 2017,
  • [34] Numerical study on the thermal stratification characteristics of AP1000 pressurizer surge line
    Wang, Mingjun
    Feng, Tangtao
    Fang, Di
    Hou, Ting
    Tian, Wenxi
    Su, G. H.
    Qiu, Suizheng
    ANNALS OF NUCLEAR ENERGY, 2019, 130 : 8 - 19
  • [35] A Study on Application of Fatigue Correction Factor for Environmental Fatigue Evaluation of Pressurizer Surge Line
    Yang, Jun-Seog
    Park, Chi-Yong
    Kang, Seon-Ye
    TRANSACTIONS OF THE KOREAN SOCIETY OF MECHANICAL ENGINEERS A, 2009, 33 (10) : 1151 - 1157
  • [36] Numerical Analysis of the Weld Joint Resulting Influence on the Pressurizer Surge Line Stress Distribution
    Yang, Yang
    Xia, Hong
    Zeng, Xian
    Yu, Dali
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 1, 2014,
  • [37] Fluid-structure interaction analysis for pressurizer surge line subjected to thermal stratification
    Kang, Dong Gu
    Jhung, Myung Jo
    Chang, Soon Heung
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (01) : 257 - 269
  • [38] Numerical investigation on turbulent penetration and thermal stratification for the in-surge case of the AP1000 pressurizer surge line
    Tang, Bin
    Zhou, Yuan
    NUCLEAR ENGINEERING AND DESIGN, 2021, 378
  • [39] Application of Heat Conduction Inverse Problem in Thermal Stratification Test for Pressurizer Surge Line
    Wang X.
    Ai H.
    Zhang Y.
    Yuan Y.
    Wu Y.
    Li L.
    Hedongli Gongcheng/Nuclear Power Engineering, 2020, 41 : 74 - 78
  • [40] Flooding in the pressurizer surge line of AP600 plant and analyses of APEX data
    Westinghouse Electric Company, Nuclear Services Division, Box 355, Pittsburgh, PA 15230, United States
    Nucl Eng Des, 1 (45-58):