Experimental investigation of pressure fluctuation and steam transport under SGTR accident in Lead-cooled Fast Reactors

被引：7
|
作者：
Yu, Qifan [1 ]
Fang, Yuliang [1 ]
Zhao, Yafeng [1 ]
Qiu, Suizheng [1 ]
Wang, Chenglong [1 ]
Zhang, Dalin [1 ]
Tian, Wenxi [1 ]
Su, G. H. [1 ]
机构：
[1] Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Shaanxi Key Lab Adv Nucl Energy & Technol, Xian 710049, Shaanxi, Peoples R China
来源：
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER | 2023年 / 207卷
基金：
中国国家自然科学基金;
关键词：
Lead-cooled Fast Reactors; SGTR; Multiphase flow; Thermal-hydraulic experiment; Pressure fluctuation; Steam transport; WATER-JET INJECTION; COOLANT; DESIGN;
D O I：
10.1016/j.ijheatmasstransfer.2023.123988
中图分类号：
O414.1 [热力学];
学科分类号：
摘要：
Transient multiphase flow phenomenon of hyperbaric water jetting into lead-based eutectic (LBE) is of significant importance for safety analysis of Lead-cooled Fast Reactors (LFRs). In order to investigate the thermal-hydraulic parameters under Steam Generator Tube Rupture (SGTR) Accident in LFRs, the Lead-bismuth Eutectic Steam generator tube rupture Test facility (LEST) was built and the effects of (1) initial pressure peak, (2) pressure rising, (3) steam cavity migration in reaction vessel were evaluated. Under the present experimental and theoretical analysis, the results showed that the maximum pressure peak of 2.93 MPa occurred under the condition of 10 MPa water initial pressure which is the highest experi-mental requirements of reactor second system, and the accident consequence of pressure peak together with the maximum rising rate 2.001 MPa/s might be the most serious. Floating rate of steam cavity was different in radial direction, and was affected by water pressure and LBE level height. The analysis results will provide severity assessment for safety design, accident forecasting and engineering guidance of LFRs. (c) 2023 Published by Elsevier Ltd.
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页数：16
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