OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1981 · 18 citations · 0 references
EngineeringNuclear EngineeringHeat TransferNuclear MaterialsReactor PhysicsReactivity ControlReactor Core DesignReactor DesignTemperature Control In ReactorsThermal-hydraulic ControlThermal-hydraulic Safety AnalysisCore Thermal-hydraulic DesignCore Thermal-hydraulic ResponsePressurized Water ReactorsReactivityReactivity Control In Pressurized Water ReactorsTechnical FeasibilityThermal-hydraulic DesignThermal-hydraulic Performance
This report summarizes the technical feasibility of employing a UO/sub 2/-PuO/sub 2/ core with a very low water volume fraction in an Oconee-type PWR. Studies that addressed questions related to core reactivity control, thermal-hydraulic behavior, and response to a loss-of-coolant accident are described. The analyses performed support the conclusion that the use of a tight-lattice core in a PWR appears in principle to be technically feasible.