Validation of INTRA against the upgraded ingress-of-coolant event tests

Abstract

The code INTRA (IN-vessel TRansient Analysis), is one of the reference codes specified by the ITER Joint Central Team and the European Community for safety analyses of Tokamak type fusion reactors. INTRA has been developed to analyse integrated behaviours such as pressurisation, chemical reactions and temperature transients inside the plasma chamber and adjacent rooms, following postulated accidents, e.g. ingress of coolant water or air. The integrated ICE (Ingress-of-Coolant Events) tests are performed to investigate International Thermonuclear Experimental Reactor (ITER) safety design parameters and provide experimental data to validate safety analysis codes, such as INTRA. The ICE tests are focused on the Category IV multiple first wall pipe break events. Major test items of ICE are pressure transient, two-phase flow characteristics and pressure drop through the divertor, condensation effects in the suppression tank and functional performance of the pressure suppression system. The present work addresses the INTRA model of the upgraded ICE facility and the calculation results of two, out of eight, tests from the third test series. The results show a good agreement with the experiment in predicting pressure and temperature transients as well as maximum pressure values in the system.