Nuclear Applications and Technology · 1970 · 29 citations · 4 references
EngineeringNuclear EngineeringNuclear Fuel CycleNuclear MaterialsReactor PhysicsEnergy ConversionNuclear Fuel ChemistryReactor Core DesignReactor DesignReactor KineticsUranium ConversionBreeding Ratio AnalysisChemical ProcessingConversion Ratio AnalysisMolten Salt Breeder SystemsMolten Salt ReactorsPlutonium Fissile InventoryReactor Core PhysicsReactor Operation
As presently conceived at Oak Ridge National Laboratory and described in this issue, the single-fluid Molten-Salt Breeder Reactor, operating on the 232Th-233 U fuel cycle and based on a reference design, has a breeding ratio of ~1.06, specific fissile inventory of 1.5 kg/MW(e), a fuel doubling time of ~20 years, and fuel cycle costs of ~0.7 mill/kWh(e). Start-up may be accomplished with either enriched uranium or plutonium, with little effect on fuel cost; the breeding ratio, averaged over reactor life, is reduced 0.01 to 0.02 relative to the equilibrium cycle.Operated as a converter, with limited chemical processing, the reactor may have a conversion ratio in the range 0.8 to 0.9 with fuel cycle costs of 0.7 to 0.9 mill/kWh(e).
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W.R. Grimes · Nuclear Applications and Technology · 1970 · 225 citations
Engineering Development of the MSBR Fuel Recycle
M.E. Whatley, L.E. McNeese, W. L. Carter et al. · Nuclear Applications and Technology · 1970 · 58 citations
Natural Sciences, Chemical Engineering, Nuclear Engineering +14