Nuclear analysis of DEMO water-cooled blanket based on sub-critical water condition

Liu, C.; Tobita, Kenji; Uto, Hiroyasu; Someya, Yoji; Takase, Haruhiko; Asakura, Nobuyuki

For the water-cooled solid blanket of DEMO, the nuclear analysis was performed based on present cooling piping system. Especially, the neutron load and temperature distribution was calculated. Further more, the local TBR was optimized by changing the material proportion for each level. It was confirmed the size of cooling loop and cooling pipe at relevant inlet velocity. The pipe pitches would vary with level which is related to the blanket structure design. Nuclear heat distribution is the base to decide the distribution of cooling pipe positions. It was found the local TBR of blanket would be dropped down along with the level rising which was mainly depended on the thickness of beryllium variation. Finally, the layout of cooling pipes for each level was obtained.