Experimental study on two-phase flow natural circulation in a core catcher cooling channel for EU-APR1400 using air-water system

被引:7
|
作者
Song, Ki Won [1 ,2 ]
Thanh Hung Nguyen [3 ]
Ha, Kwang Soon [2 ]
Kim, Hwan Yeol [2 ]
Song, Jinho [2 ]
Park, Hyun Sun [1 ]
Revankar, Shripad T. [1 ,3 ]
Kim, Moo Hwan [1 ,4 ]
机构
[1] POSTECH, Div Adv Nucl Engn, Pohang 790784, South Korea
[2] Korea Atom Energy Res Inst, Daejeon 34057, South Korea
[3] Purdue Univ, Sch Nucl Engn, 400 Cent Dr, W Lafayette, IN 47906 USA
[4] Korea Inst Nucl Safety, Daejeon 305338, South Korea
基金
新加坡国家研究基金会;
关键词
Core catcher; Two-phase natural circulation; Flow regimes in large channels; Local void fraction; Flow transition; BOILING HEAT-TRANSFER; INCLINED SURFACES; VESSEL; LIQUID; COOLABILITY; PRESSURE;
D O I
10.1016/j.nucengdes.2017.03.009
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
Ex-vessel core catcher cooling system driven by natural circulation is designed using a full scaled air-water system. A transparent half symmetric section of a core catcher coolant channel of a pressurized water reactor was designed with instrumentations for local void fraction measurement and flow visualization. Two designs of air-water top separator water tanks are studied including one with modified 'super-step' design which prevents gas entrainment into down-comer. In the experiment air flow rates are set corresponding to steam generation rate for given corium decay power. Measurements of natural circulation flow rate, spatial local void fraction distribution and re-wetting time near the top wall are carried out for various air flow rates which simulate boiling-induced vapor generation. Since heat transfer and critical heat flux are strongly dependent on the water mass flow rate and development of two-phase flow on the heated wall, knowledge of two-phase flow characteristics in the coolant channel is essential. Results on flow visualization showing two phase flow structure specifically near the high void accumulation regions, local void profiles, rewetting time, and natural circulation flow rate are presented for various air flow rates that simulate corium power levels. The data are useful in assessing the cooling capability of and safety of the core catcher system. (C) 2017 Elsevier B.V. All rights reserved.
引用
收藏
页码:75 / 88
页数:14
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