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Loss-of-Flow Test L5 on FFTF-Type Irradiated Fuel

Description: Test L5 simulated a hypothetical loss-of-flow accident in an LMFBR using three (plutonium, uranium) dioxide fuel elements of the FTR type. The test elements were irradiated before TREAT Test L5 in the General Electric Test Reactor to 8 at. % burnup at about 40 kW/m. The pre-irradiation in GETR caused a fuel-restructuring range characteristic of moderate-power structure relative to the FTR. The test transient was devised so that a power burst would be initiated at incipient cladding melting afte… more
Date: March 1978
Creator: Simms, R.; Gehl, S. M.; Lo, R. K. & Rothman, Alan B.
Partner: UNT Libraries Government Documents Department
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Irradiation of an Aluminum Alloy-Clad, Aluminum-Uranium Alloy-Fueled Plate

Description: Report issued by the Argonne National Laboratory discussing irradiation tests of an aluminum alloy-clad, aluminum-uranium alloy fuel plate. As stated in the introduction, "calculations were made to determine the lowest possible pressure which would allow the maximum possible local boiling on the plate and still assure a margin of safety against burnout" (p. 9). This report includes tables, illustrations, and photographs.
Date: July 1960
Creator: Gavin, A. P. & Crothers, C. C.
Partner: UNT Libraries Government Documents Department
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