Transient thermal-hydraulic characteristics of the lithium loop in space lithium-cooled fast reactor

摘要: The space lithium-cooled fast reactor (LFR) system incorporating the Stirling conversion power system is composed of reactor core , electromagnetic pump, gas-liquid separator, Stirling engine and heat pipe radiator. In this study, the lithium loop of the 2.4-MW space LFR was modeled based on RESYS code. Both full power and standby steady-state conditions are simulated to validate the accuracy and applicability of modeling the lithium loop. Three types of typical transient analyses are carried out, including the over-power accident, the low-power accidents, and the loss of flow accident (LOFA) in the lithium loop. The results provide valuable references for the shutdown signal setting, the operating temperature range of Stirling engine and the ground experiment for the space LFR system coupled Stirling engine.