Experimental investigation of pressure fluctuation and steam transport under SGTR accident in Lead-cooled Fast Reactors. (15th June 2023)

• Record Type: Journal Article
• Authors: Yu, Qifan; Fang, Yuliang; Zhao, Yafeng; Qiu, Suizheng; Wang, Chenglong; Zhang, Dalin; Tian, Wenxi; SU, G.H.
• Is Part Of: International journal of heat and mass transfer. Volume 207(2023)
• Publication Date: 2023-06-15
• Subjects: Lead-cooled Fast Reactors -- SGTR -- Multiphase flow -- Thermal-hydraulic experiment -- Pressure fluctuation -- Steam transport; Heat -- Transmission -- Periodicals; Mass transfer -- Periodicals; Chaleur -- Transmission -- Périodiques; Transfert de masse -- Périodiques; Electronic journals; 621.4022
• DOI: 10.1016/j.ijheatmasstransfer.2023.123988
• Languages: English
• ISSNs: 0017-9310

Abstract

Highlights: LEST was built to study transient SGTR multiphase accident of LFRs. Initial pressure peak wave was firstly captured as a potential threat to reactor. Pressure wave transmission and attenuation was fitted. Three-dimensional plot of steam cavity transport was shown. Abstract: 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 experimental 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.