Abstract
KAERI has been conducting R&D on sodium-cooled fast reactor(SFR) as a next-generation reactor, and a copper bonded steam generator(CBSG) has been proposed to minimize the occurrence of sodium-water reaction(SWR) accident in SFRs. In this paper, a development progress of a CBSG sizing analyzer(CBSGSA) code is described. A sizing and rating analysis of CBSG has been performed to set thermal-hydraulic conditions applicable to the steam generator of the TRU core system.
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