EXPERIMENTAL INVESTIGATION ON STEAM GENERATOR TUBE RUPTURE (SGTR) ACCIDENT OF LEAD-COOLED FAST REACTORS BASED ON LEST FACILITY

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<p>Whole process exploration and transient thermal-hydraulic parameters acquisition of Steam Generator Tube Rupture (SGTR) Accident are of significant importance for safety analysis of Lead-cooled Fast Reactors (LFRs). The Lead-bismuth Eutectic Steam generator tube rupture Test facility (LEST) for transient experiments of lead-based eutectic (LBE)-water-steam three-phase was built. Three thermal-hydraulic phenomena were analyzed. These include 1) initial pressure peak measured and pressure attenuation equations fitted, 2) LBE pressure rising curves and its equilibrium with water side, 3) steam cavity migration monitored by thermocouples. The latest results showed that the accident pressure in LBE side rose with a higher water initial pressure 7.5MPa. The attenuation curve of pressure peak was represented by simple harmonic vibration. Besides, the injection of supercooled water incurred temperature fluctuations in LBE pool, with an instantaneous 81.6 ℃ temperature drop near the injection nozzle, and then LBE temperature re-entered a new dynamic equilibrium.</p>

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