SAFETY ANALYSIS RESULTS FOR ITER IN-VESSEL LOSS-OF-COOLANT EVENTS

A number of postulated in-vessel loss of coolant accidents (LOCAs) ass ociated with the first wall and baffle cooling systems of the ITER det ailed design have been analyzed for the ITER Non-site Specific Safety Report (NSSR-1). A range of break sizes from one first wall tube break (1.57 x 10(-4) m(2)) to damage to all in-vessel components (0.6 m(2) break) have been examined. These events span the ITER event classifica tion from likely events to extremely unlikely events. In addition, in- vessel pipe breaks in combination with bypass of the two confinement b arriers through a generic penetration have been examined. In all cases , when the vacuum vessel pressure suppression system is activated, mos t of the radioactive inventory is carried to the suppression pool wher e it remains for the duration of the event. Releases in these events a re well within ITER release limits.