Safety studies for Japanese demo design with AINA code

Rivas, J. C.*; Nakamura, Makoto; Someya, Yoji; Takase, Haruhiko; Tobita, Kenji; de Blas, A.*; Dies, J.*; Fabbri, M.*; Riego, A.*

Safety studies of plasma-wall transients have been performed with AINA code for the Japanese DEMO design (water cooled pebble bed). The AINA code has been adapted from its original mission of performing safety studies for ITER to this new mission. A breeding blanket model has been implemented in code. The configuration has been changed to implement the design parameters of DEMO reactor. First analyses performed show the behavior of the reactor during ex-vessel LOCA transients and during overpower events.