The lead-bismuth cooled fast reactor (LFR) is one of the fourth-generation advanced reactors, which has the advantages of enhanced safety and high efficiency. However, the steam generator tube rupture (SGTR) accident is an important design-based accident in safety analysis, which may cause a severe threat to the integrity of the reactor system. In this paper, a numerical method was established to simulate the interaction of high-pressure water injection with lead-bismuth, and validated against the LIFUS5 experiment. A sensitivity analysis of the effect of water and lead-bismuth parameters on the water flow rate, vapor generation, and pressure evolution was conducted. The results indicated that the vapor generation at the early time was mainly caused by the water flash evaporation, followed by an accelerated vapor generation rate due to the enhanced heat transfer resulting from the vapor bubble fragmentation and the direct contact of lead-bismuth with water. It was found that a significant temperature gradient existed at the vapor and lead-bismuth interface. There was a pressure spike at the impact of water injection to the lead-bismuth, followed by a continuous increase of the overall pressure and the final stable pressure in the lead-bismuth vessel exceeded the initial water injection pressure. Sensitivity analysis results indicated that, as the water injection pressure increased, the water flow rate, vapor mass, and pressure in the vessel increased significantly, but the temperatures of water and lead-bismuth had little influence on the interactions.
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