Two-phase natural circulation flow of air and water in a reactor cavity model under an external vessel cooling during a severe accident

被引:39
|
作者
Park, R. J. [1 ]
Ha, K. S. [1 ]
Kim, S. B. [1 ]
Kim, H. D. [1 ]
机构
[1] Korea Atom Energy Res Inst, Taejon 305353, South Korea
关键词
D O I
10.1016/j.nucengdes.2006.03.006
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
As a part of a study on a two-phase natural circulation flow between the outer reactor vessel and the insulation material in the reactor cavity under an external reactor vessel cooling of the Advanced Power Reactor (APR) 1400, a Hydraulic Evaluation of Reactor cooling Mechanism by External Self-induced flow-HALF scale (HERMES-HALF) experiment has been performed by using the non-heating method of an air injection. This large-scale experiment uses a half-height and half-sector model of the APR1400. This experiment has been analyzed to verify and evaluate the experimental results by using the RELAP5/MOD3 computer code. The RELAP5/MOD3 results have shown that the water circulation mass flow rate is very similar to the experimental results of the HERMES-HALF, in general. Increases in the water inlet area and the water level in the reactor cavity lead to an increase in the water circulation mass flow rate. The effects of an air injection mass flow rate and the water outlet area on the water circulation mass flow rate are dependent on the water inlet area size. As the water outlet moves to a lower position, the water circulation mass flow rate increases slowly. (c) 2006 Elsevier B.V. All rights reserved.
引用
收藏
页码:2424 / 2430
页数:7
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