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  1. 1
    DESCRIPTION AND PROPOSED OPERATION OF THE FUEL CYCLE FACILITY FOR THE SECOND EXPERIMENTAL BREEDER REACTOR (EBR-II)

    DESCRIPTION AND PROPOSED OPERATION OF THE FUEL CYCLE FACILITY FOR THE SECOND EXPERIMENTAL BREEDER REACTOR (EBR-II)

    Published 1963
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  2. 2
    MOX capsule post-irradiation examination. Volume 2 Test plan for 30-GWd/MT burnup fuel.

    MOX capsule post-irradiation examination. Volume 2 Test plan for 30-GWd/MT burnup fuel.

    Published 1997
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  3. 3
    Cold vacuum drying residual free water test description

    Cold vacuum drying residual free water test description

    Published 1997
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  4. 4
    In-Pile Instrumentation Multi- Parameter System Utilizing Photonic Fibers and Nanovision

    In-Pile Instrumentation Multi- Parameter System Utilizing Photonic Fibers and Nanovision

    Published 2015
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  5. 5
    Modeling of hydride precipitation and re-orientation

    Modeling of hydride precipitation and re-orientation

    Published 2015
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  6. 6
    Review of behavior of mixed-oxide fuel elements in extended overpower transient tests in EBR-II

    Review of behavior of mixed-oxide fuel elements in extended overpower transient tests in EBR-II

    Published 1994
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  7. 7
    International Nuclear Safety Center database on thermophysical properties of reactor materials

    International Nuclear Safety Center database on thermophysical properties of reactor materials

    Published 1997
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  8. 8
    Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes

    Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes

    Published 2016
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  9. 9
    Report on fundamental modeling of irradiation-induced swelling and creep in FeCrAl alloys

    Report on fundamental modeling of irradiation-induced swelling and creep in FeCrAl alloys

    Published 2016
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  10. 10
    ORNL Interim Progress Report on Hydride Reorientation CIRFT Tests

    ORNL Interim Progress Report on Hydride Reorientation CIRFT Tests

    Published 2016
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  11. 11
    Characterization of Tubing from Advanced ODS alloy (FCRD-NFA1)

    Characterization of Tubing from Advanced ODS alloy (FCRD-NFA1)

    Published 2016
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  12. 12
    Metallic fuel safety assessment

    Metallic fuel safety assessment

    Published 1989
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  13. 13
    Thermocouple tests a quick-look report on failures during loss-of-fluid tests L2-6 (LOFT L2-6)

    Thermocouple tests a quick-look report on failures during loss-of-fluid tests L2-6 (LOFT L2-6)

    Published 1984
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  14. 14
    STAINLESS STEEL PROCESS WASTES I. REMOVAL OF ALLOY METALS FROM WASTE SOLUTIONS BY MERCURY CATHODE ELECTROLYSIS.

    STAINLESS STEEL PROCESS WASTES I. REMOVAL OF ALLOY METALS FROM WASTE SOLUTIONS BY MERCURY CATHODE ELECTROLYSIS.

    Published 1960
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  15. 15
    EXPERIMENTAL ORGANIC COOLED REACTOR CONCEPTUAL DESIGN

    EXPERIMENTAL ORGANIC COOLED REACTOR CONCEPTUAL DESIGN

    Published 1959
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  16. 16
    DISSOLVER FOR NATURAL URANIUM FUEL ELEMENTS

    DISSOLVER FOR NATURAL URANIUM FUEL ELEMENTS

    Published 1958
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  17. 17
    Demonstration of a high burnup heterogeneous core using ferritic/martensitic materials

    Demonstration of a high burnup heterogeneous core using ferritic/martensitic materials

    Published 1986
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  18. 18
    Performance of titanium stabilized D9 cladding and ducts

    Performance of titanium stabilized D9 cladding and ducts

    Published 1986
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  19. 19
    Monthly highlights for Office of Nuclear Regulatory research programs at Oak Ridge National Laboratory

    Monthly highlights for Office of Nuclear Regulatory research programs at Oak Ridge National Laboratory

    Published 1975
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  20. 20
    Co-processing of zirconium and aluminum fuels during 1972

    Co-processing of zirconium and aluminum fuels during 1972

    Published 1973
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