Safety Analysis of Demonstration Fast Reactor Core Melt Collector

For high temperature structural integrity question of the demonstration fast reactor core melt collector, strategy effectiveness valuation method (IVR-DOE10460) of core melt retention in reactor pressure vessel was adopted. The 316H constitutive model, multi axis correction and concrete evaluation method were established. By collecting the material data related to 316H steel in ASME code and R66 material data manual, the input data were determined. On this basis, the stress and strain analysis of the reactor core melt collector under the accumulation of core melts was carried out by using the finite element analysis software ABAQUS, and the creep strength of the reactor core melt collector was checked based on time fraction method and ductility exhaustion method (strain fraction method). The results of finite element analysis show that the core melt collector can meet the requirements of creep strength test with time fraction and strain fraction less than 1 within design lifetime and meet the functional requirement with a vertical displacement less than design target. The reactor core melt collector can maintain structural integrity after serious accident of core melts.