1-D Two-phase Flow Investigation for External Reactor Vessel Cooling

被引:0
|
作者
Kim, Jae-Cheol
Ha, Kwang-Soon
Park, Rae-Joon
Cho, Young-Rho
Kim, Sang-Baik
Kim, Sin
机构
关键词
Natural Circulation Flow; External Reactor Vessel Cooling; Two-Phase Flow;
D O I
10.3795/KSME-B.2007.31.5.482
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
When a molten corium is relocated in a lower head of a reactor vessel, the ERVC (External Reactor Vessel Cooling) system is actuated as coolant is supplied into a reactor cavity to remove a decay heat from the molten corium during a severe accident. To achieve this severe accident mitigation strategy, the two-phase natural circulation flow in the annular gap between the external reactor vessel and the insulation should be formed sufficiently by designing the coolant inlet/outlet area and gap size adequately on the insulation device. For this reason, one-dimensional natural circulation flow tests and the simple analysis were conducted to estimate the natural circulation flow under the ERVC condition of APR1400. The experimental facility is one-dimensional and scaled down as the half height and 1/238 channel area of the APR1400 reactor vessel. The calculated circulation flow rate was similar to experimental ones within about +/- 15% error bounds and depended on the form loss due to the inlet/outlet area.
引用
收藏
页码:482 / 490
页数:9
相关论文
共 50 条
  • [1] Loop analysis of a natural circulation two-phase flow under an external reactor vessel cooling
    Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Daejeon 305-353, Korea, Republic of
    [J]. Int. Commun. Heat Mass Transf., 2008, 8 (1001-1006):
  • [2] Analytical evaluation of two-phase natural circulation flow characteristics under external reactor vessel cooling
    Park, Jong Woon
    [J]. ANNALS OF NUCLEAR ENERGY, 2009, 36 (11-12) : 1668 - 1675
  • [3] One-dimensional experiments of a natural circulation two-phase flow under an external reactor vessel cooling
    Kim, Jae Cheol
    Ha, Kwang Soon
    Park, Rae Joon
    Kim, Sang Baik
    Hong, Seong Wan
    [J]. INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, 2008, 35 (06) : 716 - 722
  • [4] Two-phase natural circulation flow of air and water in a reactor cavity model under an external vessel cooling during a severe accident
    Park, R. J.
    Ha, K. S.
    Kim, S. B.
    Kim, H. D.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2006, 236 (23) : 2424 - 2430
  • [5] The study of a reactor cooling pump under two-phase flow
    Wang, P.
    Yuan, S. Q.
    Wang, X. L.
    Zhang, F.
    [J]. INTERNATIONAL SYMPOSIUM OF CAVITATION AND MULTIPHASE FLOW (ISCM 2014), PTS 1-6, 2015, 72
  • [6] A study using RELAP5 on capability and instability of two-phase natural circulation flow under passive external reactor vessel cooling
    Zhao Guozhi
    Cao Xinrong
    Shi Xingwei
    [J]. ANNALS OF NUCLEAR ENERGY, 2013, 60 : 115 - 126
  • [7] Two-phase flow measurements and observations in a cooling panel of the reactor cavity cooling system
    Vaghetto, R.
    Yang, S.
    Hodge, D.
    Hassan, Y.
    [J]. PROGRESS IN NUCLEAR ENERGY, 2021, 131
  • [8] Investigation of External Reactor Pressure Vessel Cooling with ATHLET-CD
    Pandazis, Peter
    Weber, Sebastian
    [J]. 25TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2016), 2016,
  • [9] NUMERICAL SIMULATION OF 1-D UNSTEADY TWO-PHASE FLOWS WITH SHOCKS
    吴清松
    王柏懿
    [J]. Applied Mathematics and Mechanics(English Edition), 1992, (07) : 629 - 635
  • [10] Analysis of bedform instability with 1-D two-phase morphodynamical models
    Greco, Massimo
    Iervolino, Michele
    Vacca, Andrea
    [J]. ADVANCES IN WATER RESOURCES, 2018, 120 : 50 - 64