Study of loss-of-coolant events in a water-cooled tokamak DEMO

Nakamura, Makoto; Tobita, Kenji; Someya, Yoji; Tanigawa, Hisashi; Sakamoto, Yoshiteru; Gulden, W.*

Thermohydraulic responses of the DEMO to in-vessel and ex-vessel loss of the primary coolant have been analyzed by the MELCOR code. The analyses have identified possible event sequences following such accidents, their time scales and loads to the confinement barriers of the radioactive materials. On basis of the analyses results, measures to reduce the loads challenging the confinement barrier are proposed.