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  1. 1
    Development and Validation of Accident Models for U<sub>3</sub>Si<sub>2</sub>

    Development and Validation of Accident Models for U<sub>3</sub>Si<sub>2</sub>

    Published 2016
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  2. 2
    RELEASE AND TRANSPORT OF FISSION PRODUCTS RELEASED FROM FUEL PINS IRRADIATED TO 20,000 MWD/TON SUMMARY REPORT OF NSPP RUN 15.

    RELEASE AND TRANSPORT OF FISSION PRODUCTS RELEASED FROM FUEL PINS IRRADIATED TO 20,000 MWD/TON SUMMARY REPORT OF NSPP RUN 15.

    Published 1972
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  3. 3
    Supplemental Thermal-Hydraulic Transient Analyses of BR2 in Support of Conversion to LEU Fuel

    Supplemental Thermal-Hydraulic Transient Analyses of BR2 in Support of Conversion to LEU Fuel

    Published 2016
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  4. 4
    Validation of COMMIX with Westinghouse AP-600 PCCS test data

    Validation of COMMIX with Westinghouse AP-600 PCCS test data

    Published 1993
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  5. 5
    Downward flow of water with entrained air in a nonuniformaly heated subdivided annulus

    Downward flow of water with entrained air in a nonuniformaly heated subdivided annulus

    Published 1992
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  6. 6
    Thermal-hydraulic analysis of the HFIR (High Flux Isotope Reactor)

    Thermal-hydraulic analysis of the HFIR (High Flux Isotope Reactor)

    Published 1990
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  7. 7
    An empirical investigation of operator performance in cognitively demanding simulated emergencies

    An empirical investigation of operator performance in cognitively demanding simulated emergencies

    Published 1994
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  8. 8
    APT Blanket System Loss-of-Coolant Analysis Based on Initial Conceptual Design - Case 2 External HR Break HR Break at Pump Outlet with Pump Trip.

    APT Blanket System Loss-of-Coolant Analysis Based on Initial Conceptual Design - Case 2 External HR Break HR Break at Pump Outlet with Pump Trip.

    Published 1998
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  9. 9
    Recriticality energetics of a hypothetical water reflood accident in a damaged light water reactor

    Recriticality energetics of a hypothetical water reflood accident in a damaged light water reactor

    Published 1997
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  10. 10
    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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  11. 11
    Metallic fuel safety assessment

    Metallic fuel safety assessment

    Published 1989
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  12. 12
    One-dimensional modeling of radial heat removal during depressurized heatup transients in modular pebble-bed and prismatic high temperature gas-cooled reactors

    One-dimensional modeling of radial heat removal during depressurized heatup transients in modular pebble-bed and prismatic high temperature gas-cooled reactors

    Published 1984
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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
    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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  15. 15
    NUCLEAR SAFETY PROGRAM. Annual Progress Report for Period Ending December 31, 1970

    NUCLEAR SAFETY PROGRAM. Annual Progress Report for Period Ending December 31, 1970

    Published 1971
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  16. 16
    EFFECT OF IRRADIATION ON THE FAILURE OF ZIRCALOY-CLAD FUEL RODS.

    EFFECT OF IRRADIATION ON THE FAILURE OF ZIRCALOY-CLAD FUEL RODS.

    Published 1972
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  17. 17
    THERMAL RADIATION TRANSFER OF AFTERHEAT IN MSBR HEAT EXCHANGERS.

    THERMAL RADIATION TRANSFER OF AFTERHEAT IN MSBR HEAT EXCHANGERS.

    Published 1971
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  18. 18
    Rate Theory Modeling and Simulation of Silicide Fuel at LWR Conditions

    Rate Theory Modeling and Simulation of Silicide Fuel at LWR Conditions

    Published 2016
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  19. 19
    Use of radiography to monitor structural movement in GCFR-CFTL fuel rod bundles

    Use of radiography to monitor structural movement in GCFR-CFTL fuel rod bundles

    Published 1979
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  20. 20
    Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Early Demonstration

    Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Early Demonstration

    Published 2015
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