Open AccessCORE PARAMETER STUDY FOR A 300-MW SODIUM GRAPHITE REACTOR
Author(s) -
W.P. Corcoran
Publication year - 1959
Language(s) - English
Resource type - Reports
DOI - 10.2172/4054639
Subject(s) - nuclear engineering , graphite , sodium cooled fast reactor , core (optical fiber) , materials science , nuclear reactor core , range (aeronautics) , environmental science , engineering , metallurgy , composite material
A core parameter study of the operating costs was performed for a 300- Mwe sodium graphite reactor, a scale-up of the Hallam Power Reactor. The results of the study indicate that the core design is nsar optimum and that core modifications would reduce the power costs by less than 5%. The lattice spacing, fuel rod diameter, and sodium flow can be varied within a rather broad range without significant changes in power generation costs. The effect of the fuel cladning thickness is more significant; fuel cycle costs can be reduced if stainless steel canning is replaced with zirconium canning. Use of UC in place of uraniummolybdenum fuel would also permit cost reductions. (D.L.C.