Showing 1 - 8 results of 8 for search 'Jenks, G. H. (Glenn Herbert), 1916-', query time: 0.06s Refine Results
  1. 1
    In-pile loop investigations of corrosion of Zircaloy-2 and other possible reactor materials in 0.04 m UO₂SO₄ at 280°C

    In-pile loop investigations of corrosion of Zircaloy-2 and other possible reactor materials in 0.04 m UO₂SO₄ at 280°C by Jenks, G. H. (Glenn Herbert), 1916-

    Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1960
    Format: Government Document Book


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  2. 2
    Determination of the effect of high excess H₂SO₄ concentrations on the radiation-induced corrosion of zirconium and titanium alloys in 0.17 m UO₂SO₄

    Determination of the effect of high excess H₂SO₄ concentrations on the radiation-induced corrosion of zirconium and titanium alloys in 0.17 m UO₂SO₄ by Jenks, G. H. (Glenn Herbert), 1916-

    Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1962
    Format: Government Document Book


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  3. 3
    Measurement of the half-life and mean energy of tritium decay

    Measurement of the half-life and mean energy of tritium decay by Jenks, G. H. (Glenn Herbert), 1916-

    Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1950
    Format: Government Document Book


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  4. 4
    Review and correlation of in-pile zircaloy-2 corrosion data and a model for the effect of irradiation

    Review and correlation of in-pile zircaloy-2 corrosion data and a model for the effect of irradiation by Jenks, G. H. (Glenn Herbert), 1916-

    Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1961
    Format: Government Document Book


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  5. 5
    In-pile loop corrosion experiments with uranyl sulfate solutions at 235 and 250°C

    In-pile loop corrosion experiments with uranyl sulfate solutions at 235 and 250°C by Jenks, G. H. (Glenn Herbert), 1916-

    Oak Ridge, Tenn. : U.S. Atomic Energy Commission, 1963
    Format: Government Document Book


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  6. 6
    In-pile radiation corrosion experiments with zirconium, titanium, and steel alloys in 0.17 m UO₂SO₄ solutions at 280°C

    In-pile radiation corrosion experiments with zirconium, titanium, and steel alloys in 0.17 m UO₂SO₄ solutions at 280°C by Jenks, G. H. (Glenn Herbert), 1916-

    Format: Government Document Book


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  7. 7
    Effects of temperature, temperature gradients, stress, and irradiation on migration of brine inclusions in a salt repository

    Effects of temperature, temperature gradients, stress, and irradiation on migration of brine inclusions in a salt repository by Jenks, G. H. (Glenn Herbert), 1916-

    Oak Ridge, Tenn. : [Springfield, Va.] : Dept. of Energy, Oak Ridge National Laboratory ; [for sale by the National Technical Information Service], 1979
    Format: Government Document Book


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  8. 8
    A critique of "Brine migration in salt and its implications in geologic disposal of nuclear waste," Oak Ridge National Laboratory report 5818, by G.H. Jenks and H.C. Claiborne

    A critique of "Brine migration in salt and its implications in geologic disposal of nuclear waste," Oak Ridge National Laboratory report 5818, by G.H. Jenks and H.C. Claiborne by Roedder, Edwin, 1919-

    [Reston, Va.] : The Survey, 1982
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    Format: Government Document Book


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