METHOD FOR THERMAL-HYDRAULIC SAFETY ANALYSIS FOR NUCLEAR REACTOR VESSEL USING THREE-DIMENSIONAL COMPUTATIONAL FLUID DYNAMICS(CFD)

摘要

PURPOSE: A method for analyzing a thermal hydraulic safety for a nuclear reactor is provided to rapidly perform a transient state analysis using a system code. CONSTITUTION: A three dimensional CAD shape about a reactor floating area is generated(S110). A nodalization position about a reactor fluidic channel is set(S120). The shape information of the reactor fluid channel is generated based on the nodalization position(S130). The thermal hydraulic calculation and a pressure loss coefficient calculation per node are performed(S140). The thermal hydraulic calculation of a reactor system is performed using a system code(S150). The thermal hydraulic calculation result through the three dimensional CFA analysis is compared with the thermal hydraulic calculation result(S160). The nodization information of the system code is optimized(S180).