THE NEXT-GENERATION OF FAST-REACTORS

The results of computational and design studies of a 1200 MWe lead-coo led pool-type fast reactor with U-Pu nitride fuel based on the same pr inciples as the previously considered BREST-300 design (Adamov, E.O., Orlov, V.V., Filin et al. Proc. Int. Topical Meeting on Advanced React ors Safety, ARS'94, Pittsburgh, USA, 1994, pp. 509-516.) are presented . In connection with a capacity increase and to ensure full implementa tion of the LCFR concept merits in the BREST-1200 design, a number of new solutions have been accepted compared with the more conservative i nitial design. (C) 1997 Elsevier Science S.A.