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Report No.
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Development of a nuclear-thermal-coupled analysis code for blanket design

Tanigawa, Hisashi; Gwon, H.; Kawamura, Yoshinori

JAEA is developing blanket with a water-cooled ceramic breeder concept. The blanket has a box structure made of reduced-activation ferritic/martensitic steels, and pebbles of tritium breeding and neutron multiplier materials are packed into the box. To remove nuclear heating and surface heat flux, the box structure has built-in cooling paths and cooling pipes are inserted into the packed pebble beds. The configuration of these materials has to be designed so that both necessity tritium capability and allowable material temperatures are kept. A two-dimensional nuclear-thermal-coupled analysis code has been developed for the design activity. The code gives us decay heat distribution and its time dependency in the blanket in addition to the nuclear and thermal property of the blanket under normal operation. Functions of the code and procedure how to use the obtained values in the design are reported.

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