Experiment investigation on pool boiling of the modelled spent fuel tube bundle under partial dry-out conditions

被引:0
|
作者
Lu, Daogang [1 ]
Gao, Shang [1 ]
Zhong, Yuhang [1 ]
Wang, Han [1 ]
Cao, Qiong [1 ]
Xiong, Zhenqin [2 ]
机构
[1] North China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China
[2] Shanghai Jiao Tong Univ, Sch Nucl Sci & Engn, Shanghai 200240, Peoples R China
关键词
Spent fuel pool; Dry-out; Two-phase flow; Heat transfer coefficient; Safety criterion; ROD BUNDLE; FLOW; PREDICTION;
D O I
10.1016/j.anucene.2018.08.013
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
Under normal conditions, the decay heat of the spent fuel can be removed by the forced-circulation cooling system of the spent fuel pool. In the case of a system failure, the water level in the pool will be gradually decreased owing to an evaporation of the water, and the spent fuel bundles may be exposed to air, i.e., a dry out. Since the Fukushima accident, researchers have been paying significant attention to the safety of the spent fuel under such dry-out conditions. To study the boiling behaviour of the spent fuel bundle under a partial dry-out condition, an experimental investigation has been carried out. A newly constructed 9 x 9 heated tube bundle with the same geometry as the prototype spent fuel assembly in an AP1000 was used as the test section. Two-phase flow patterns were recorded. The heat transfer coefficient of the rods in different locations was obtained. A temperature fluctuation was observed at the beginning of the dry-out process mainly owing to the reduced heat transfer effectiveness of the steam. Although the maximum wall temperature (about 570 degrees C) exceeded the safety criterion when 50% of the tube bundle at the top end was exposed to air, the bundle maintained its integrity. (C) 2018 Elsevier Ltd. All rights reserved.
引用
收藏
页码:461 / 467
页数:7
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