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Report No.

Fuel and Core Design Study of the Sodium-cooled Fast Reactors; Studies on Metallic Fuel Cores in the JFY2002

Sugino, Kazuteru; Mizuno, Tomoyasu; Takaki, Naoyuki

Based on the results obtained in the former feasibility study, the metallic fueled core of ordinary-type, that is, 2-region homogeneous core, has been established aiming at the improvement in the core performance, and subsequent comparison has been performed with the mixed oxide fueled core. Further, the attractive concept of the metallic fueled core of high outlet temperature has been constructed which has good nuclear features as a metallic fueled core and has identical outlet temperature to mixed oxide fuelled core. Following items have been found as a result of the investigation on the ordinary-type core.- The metallic fueled core whose maximum fast neutron fluence (En$$>$$0.1MeV) is set identical (5$$times$$10$$^{23}$$n/cm$$^{2)}$$to the mixed oxide fueled cores with core discharge burnup 150GWd/t has sufficient core performances as a metallic fueled core, e.g. higher breeding ratio and longer operation period compared with mixed oxide fueled cores, but the core discharge burnup is limited up to 100GWd/t. However effective discharge burnup including the contribution of the blanket region is comparative to mixed oxide cores under the same breeding ratio condition.- In order to enlarge the core discharge burnup to 150GWd/t keeping the core performance identical to above mentioned core's, the irradiation deformation of structural material should be reduced to that of mixed oxide fueled cores. Further the maximum fast neutron fluence reaches to 7 - 8$$times$$10$$^{23}$$n/cm$$^{2}$$(En$$>$$0.1MeV). The investigations on the core of high outlet temperature have clarified following items.



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