Experimental Studies of Transient Effects in Fast Reactor Fuels

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Description

An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO₂ fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F. Multiple transient damage to the cladding is likely for transients above the melting point of the fuel.

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vi, 74 p. : ill. (some folded) ; 28 cm.

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Field, J. H. November 15, 1962.

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Description

An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO₂ fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F. Multiple transient damage to the cladding is likely for transients above the melting point of the fuel.

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vi, 74 p. : ill. (some folded) ; 28 cm.

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  • November 15, 1962

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  • Jan. 19, 2015, 5:58 a.m.

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Field, J. H. Experimental Studies of Transient Effects in Fast Reactor Fuels, report, November 15, 1962; Oak Ridge, Tennessee. (digital.library.unt.edu/ark:/67531/metadc101082/: accessed October 17, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.