Thermal–Hydraulic Analysis of ITER Component Cooling Water System Loop 2B

Abstract

ITER cooling water system includes Tokamak cooling water system, component cooling water system (CCWS), chilled water system and the heat rejection system. The CCWS is further divided into CCWS-1, CCWS-2A, CCWS-2B, CCWS-2C, and CCWS-2D loops to provide independent chemical control and to prevent galvanic corrosion among the different clients’ materials (e.g. Cu, Al). The CCWS-2B is responsible to remove heat load generated by coil power supply components and the neutral beam injectors and diagnostics system during all the phases: commissioning, testing and conditioning and plasma operation. A CCWS-2B thermal–hydraulic analysis model was developed, by using the AFT Fathom code, to conduct the steady state thermal–hydraulic analysis of the system. In this thermal–hydraulic analysis model, the critical path with the largest pressure loss was used to size the pump head has been identified and the pressure loss on the control valve were used to establish the required flow balance at each piping connection points. This paper presents the results of this thermal hydraulic analysis which was composed by required pump head of the CCWS-2B loop and the main thermal–hydraulic parameters for each client (i.e. flow rate, velocities, pressure drops and outlet temperatures).