Experimental Studies of Transient Effects in Fast Reactor Fuels. Series I. UO$sub 2$ Irradiations

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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 UO/sub 2/ 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. (auth)

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79 pages

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Field, J. H. November 15, 1962.

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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 UO/sub 2/ 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. (auth)

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79 pages

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Other Information: Orig. Receipt Date: 31-DEC-63

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  • November 15, 1962

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  • Oct. 18, 2017, 7:39 a.m.

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Field, J. H. Experimental Studies of Transient Effects in Fast Reactor Fuels. Series I. UO$sub 2$ Irradiations, report, November 15, 1962; San Jose, California. (https://digital.library.unt.edu/ark:/67531/metadc1026351/: accessed July 7, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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