
doi: 10.2172/6863540
The report presents refined methods for calculation of fuel temperatures in PuO/sub 2/-UO/sub 2/ fuel in Fast Breeder Reactor (FBR) fuel pins. Of primary concern is the calculation of the temperature changes across the fuel-to-cladding gap of pins with fuel burnups that range from 60 to 10,900 MWd/MTM (0.006 to 1.12 at.%). Described in particular are: (1) a proposed set of heat transfer formulations and corresponding material properties for modeling radial heat transfer through the fuel and cladding; and (2) the calibration of a fuel-to-cladding gap conductance model, as part of a thermal performance computer code (SIEX-M1) which incorporates the proposed heat transfer expressions, using integral thermal performance data from two unique in-reactor experiments. The test data used are from the HEDL P-19 and P-20 experiments which were irradiated in the Experimental Breeder Reactor Number Two (EBR-II), for the Hanford Engineering Development Laboratory (HEDL).
Test Reactors 220600* -- Nuclear Reactor Technology-- Research, Fuel Pins, Mathematical Models, Sodium Cooled Reactors, Fftf Reactor, Test & Experimental Reactors, 21 Specific Nuclear Reactors And Associated Plants, Heat Transfer, Reactors, Energy Transfer, Research And Test Reactors, Fast Reactors, Epithermal Reactors, Calibration, Temperature Distribution, Fuel Elements, Research Reactors, Reactor Components, Liquid Metal Cooled Reactors
Test Reactors 220600* -- Nuclear Reactor Technology-- Research, Fuel Pins, Mathematical Models, Sodium Cooled Reactors, Fftf Reactor, Test & Experimental Reactors, 21 Specific Nuclear Reactors And Associated Plants, Heat Transfer, Reactors, Energy Transfer, Research And Test Reactors, Fast Reactors, Epithermal Reactors, Calibration, Temperature Distribution, Fuel Elements, Research Reactors, Reactor Components, Liquid Metal Cooled Reactors
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