Modeling the thermal effects of fabricated fuel-to-cladding gap in fast reactor fuel Public Deposited

http://ir.library.oregonstate.edu/concern/graduate_thesis_or_dissertations/d217qt28w

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  • This report presents a refined method for the calculation of fuel centerline temperatures and the linear-heat-rating-to-incipient melting, ' Q'[subscript m], of mixed-oxide fuel typical of that to be used in the Fast Flux Test Facility and in Liquid Metal Fast Breeder Reactors. Of primary concern are the effects of the fabricated fuel-to-cladding gap and accumulated burnup up to 10,900 MWd/MTM (1.1 At%) on the thermal performance of the fuel pins. Specifically described in this report are: 1) The analysis and normalization of fuel thermal performance data from two unique fast reactor fuel tests. The effect of fabricated gap size on "integral" Q'[subscript m] is developed. 2) A proposed set of heat transfer formulations and corresponding material properties for modeling the radial heat transfer path through the fuel and cladding. 3) The calibration of a fuel-to-clodding gap conductance model, which is part of a thermal performance computer code incorporating the expressions from item 2, to the data developed from the analyses in item 1. The data used in this study are from the HEDL P-19 and P-20 experiments which were irradiated in the Experimental Breeder Reactor 2, EBR-II, for the Hanford Engineering Development Laboratory, HEDL.
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  • description.provenance : Approved for entry into archive by Patricia Black(patricia.black@oregonstate.edu) on 2013-10-30T15:08:04Z (GMT) No. of bitstreams: 1 BakerRonaldB1977.pdf: 6534025 bytes, checksum: 4093fd8c8264af294329bc437bd1b84d (MD5)
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