The next generation of fast reactors Original Research Article

The results of computational and design studies of a 1200 MW, lead-cooled pool-type fast reactor with UPu nitride fuel based on the same principles as the previously considered BREST-300 design (Adamov, E.O., Orlov, V.V., Filin et al. Proc. Int. Topical Meeting on Advanced Reactors Safety, ARSʹ94, Pittsburgh, USA, 1994, pp. 509–516.) are presented. In connection with a capacity increase and to ensure full implementation of the LCFR concept merits in the BREST-1200 design, a number of new solutions have been accepted compared with the more conservative initial design.