PROPOSAL OF INTEGRATED TEST FACILITY FOR IN-VESSEL THERMOFLUID SAFETYOF FUSION-REACTORS

A vacuum vessel (VV) of a tokamak fusion reactor like the Internationa l Thermonuclear Experimental Reactor (ITER) consists the first confine ment barrier that includes the largest amount of radioactive materials such as tritium and activation products. The ingress of coolant event (ICE) is a design basis event in the ITER where water is used as the coolant. The loss of vacuum event (LOVA) is also considered as an inde pendent design basis event. Based on the results of ICE and LOVA preli minary experiments, an integrated in-vessel thermofluid test is being planned and conceptual design of the facility is in progress. The main objectives of the integrated test are to investigate the consequences of possible interaction of the ICE and the LOVA and to validate the a nalytical model of thermofluid events in the VV of the fusion reactor. This paper introduces a conceptual design of the integrated test faci lity and a testing plan.