Study on Effect of Flow Blockage at Inlet of Plate-type Fuel Element on Thermal-Hydraulic Characteristics of Reactor Core

This paper simulated the local flow blockage accident of reactor core made up of plate-type fuel with more detailed consideration of local feedback effect between thermal-hydraulics and neutron kinetics, which will help the analysis of the effect of blockage on the reactor thermal-hydraulic characteristics more practically. The simulation shows that the local blockage will cause strong feedback between neutron kinetics and thermal-hydraulics, which will lead to power decrease in the blocked channel. The fuel centreline temperature, the cladding surface temperature and the coolant average temperature will increase due to the deterioration of cooling in the blocked channel.