Experiment investigation on pool boiling of the modelled spent fuel tube bundle under partial dry-out conditions
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作者:
Lu, Daogang
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North China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China
Lu, Daogang
[1
]
Gao, Shang
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North China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China
Gao, Shang
[1
]
Zhong, Yuhang
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North China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China
Zhong, Yuhang
[1
]
Wang, Han
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North China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China
Wang, Han
[1
]
Cao, Qiong
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North China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China
Cao, Qiong
[1
]
Xiong, Zhenqin
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Shanghai Jiao Tong Univ, Sch Nucl Sci & Engn, Shanghai 200240, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China
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
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.
机构:
North China Elect Power Univ, Beijing Key Lab Pass Nucl Power Safety & Technol, Beijing, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Nucl Power Safety & Technol, Beijing, Peoples R China
Gao, Shang
Lu, Daogang
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North China Elect Power Univ, Beijing Key Lab Pass Nucl Power Safety & Technol, Beijing, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Nucl Power Safety & Technol, Beijing, Peoples R China
Lu, Daogang
Wang, Han
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机构:
North China Elect Power Univ, Beijing Key Lab Pass Nucl Power Safety & Technol, Beijing, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Nucl Power Safety & Technol, Beijing, Peoples R China
Wang, Han
Zhong, Yuhang
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North China Elect Power Univ, Beijing Key Lab Pass Nucl Power Safety & Technol, Beijing, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Nucl Power Safety & Technol, Beijing, Peoples R China
Zhong, Yuhang
[J].
PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 9,
2017,
机构:
North China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China
Lu Daogang
Yu Zongyu
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North China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China
Yu Zongyu
Zhong Yuhang
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North China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China
Zhong Yuhang
Wang Han
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机构:
North China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China
Wang Han
Zhang Yuhao
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North China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China
Zhang Yuhao
Cao Qiong
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机构:
North China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China
Cao Qiong
Gao Shang
论文数: 0引用数: 0
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机构:
North China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R ChinaNorth China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China