The management of a cooling-water supply system in a nuclear reactor is performed by valve and reactor coolant pump (RCP) control,which regulates both the pressure and the discharge between certain limits.However,the RCP has a significant unsteady flow when operating at different conditions.The unsteady pressure pulsation and radial force vector are difficult to calculate because these are affected by the transient properties of the unsteady flow.This study explores the use of a commercial Computational Fluid Dynamics (CFD) code to comprehensively estimate the unsteady flow of the RCP.The full 3D-URANS equations were solved for different flow rates,and some optimised cases for the unsteady flow were proposed.The results showed that the numerical predictions were validated with the experimental data of a model pump.The code was used to estimate the velocity streamlines,pressure pulsation and radial force vector in the steady and transient conditions.The flow rates were not equal for the inner and outer passage in the double volute casing.Additionally,the pulsation of the pressure and radial force was effectively reduced by optimising the staggered angle α.An optimal case was observed when α =30°.