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  1. 101
    Swelling of Uranium Alloys at High Exposures

    Swelling of Uranium Alloys at High Exposures

    Published 2001
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  2. 102
    Hanford Tank Waste Ion Exchange Swelling Task Technical and Quality Assurance Plan

    Hanford Tank Waste Ion Exchange Swelling Task Technical and Quality Assurance Plan

    Published 2000
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  3. 103
    FUELS, MATERIALS, AND COOLANT CHEMISTRY PROGRAMS. Quarterly Technical Progress Report, October--December 1970.

    FUELS, MATERIALS, AND COOLANT CHEMISTRY PROGRAMS. Quarterly Technical Progress Report, October--December 1970.

    Published 1971
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  4. 104
    Compressional and Shear Wave Velocities for Artificial Granular Media Under Simulated Near Surface Conditions

    Compressional and Shear Wave Velocities for Artificial Granular Media Under Simulated Near Surface Conditions

    Published 2001
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  5. 105
    MECHANISMS AND OPTIMIZATION OF COAL COMBUSTION

    MECHANISMS AND OPTIMIZATION OF COAL COMBUSTION

    Published 2000
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  6. 106
    Swelling of Aged PdTx During Hydride Phase Cycling

    Swelling of Aged PdTx During Hydride Phase Cycling

    Published 2001
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  7. 107
    SEQUESTERING CARBON DIOXIDE IN COALBEDS

    SEQUESTERING CARBON DIOXIDE IN COALBEDS

    Published 2001
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  8. 108
    NEUTRON-INDUCED SWELLING AND EMBRITTLEMENT OF PURE IRON AND PURE NICKEL IRRADIATED IN THE BN-350 AND BOR-60 FAST REACTORS

    NEUTRON-INDUCED SWELLING AND EMBRITTLEMENT OF PURE IRON AND PURE NICKEL IRRADIATED IN THE BN-350 AND BOR-60 FAST REACTORS

    Published 2002
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  9. 109
    Investigation of The Synergistic Influence of Irradiation Temperature and Atomic Displacement Rate on the Microstructural Evolution of Ion-Irradiated Model Austenitic Alloy Fe-15Cr-16Ni

    Investigation of The Synergistic Influence of Irradiation Temperature and Atomic Displacement Rate on the Microstructural Evolution of Ion-Irradiated Model Austenitic Alloy Fe-15Cr...

    Published 2002
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  10. 110
    IRRADIATION CREEP AND MECHANICAL PROPERTIES OF TWO FERRITIC-MARTENSITIC STEELS IRRADIATED IN THE BN-350 FAST REACTOR

    IRRADIATION CREEP AND MECHANICAL PROPERTIES OF TWO FERRITIC-MARTENSITIC STEELS IRRADIATED IN THE BN-350 FAST REACTOR

    Published 2002
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  11. 111
    Microstructural Changes Accompanying Annealing of Cold-Worked Uranium

    Microstructural Changes Accompanying Annealing of Cold-Worked Uranium

    Published 2002
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  12. 112
    FIELD DEMONSTRATION OF CARBON DIOXIDE MISCIBLE FLOODING IN THE LANSING-KANSAS CITY FORMATION, CENTRAL KANSAS

    FIELD DEMONSTRATION OF CARBON DIOXIDE MISCIBLE FLOODING IN THE LANSING-KANSAS CITY FORMATION, CENTRAL KANSAS

    Published 2002
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  13. 113
    Progress in development of low-enriched U-Mo dispersion fuels.

    Progress in development of low-enriched U-Mo dispersion fuels.

    Published 2002
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  14. 114
    Radiation-induced segregation and the relationship to physical properties in irradiated austenitic alloys.

    Radiation-induced segregation and the relationship to physical properties in irradiated austenitic alloys.

    Published 2002
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  15. 115
    Effects of titanium additions to austenitic ternary alloys on microstructural evolution and void swelling

    Effects of titanium additions to austenitic ternary alloys on microstructural evolution and void swelling

    Published 2003
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  16. 116
    Reactor Physics Studies of Reduced-Tantaulum-Content Control and Safety Elements for the High Flux Isotope Reactor

    Reactor Physics Studies of Reduced-Tantaulum-Content Control and Safety Elements for the High Flux Isotope Reactor

    Published 2003
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  17. 117
    ''The Incubation Period for Void Swelling and its Dependence on Temperature, Dose Rate, and Dislocation Structure Evolution''

    ''The Incubation Period for Void Swelling and its Dependence on Temperature, Dose Rate, and Dislocation Structure Evolution''

    Published 2002
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  18. 118
    Computational Design of Novel, Radiation Resistant Fusion Materials

    Computational Design of Novel, Radiation Resistant Fusion Materials

    Published 2003
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  19. 119
    Nuclear Energy Research Initiative Program (NERI) Quarterly Progress Report - New Design Equations for Swelling and Irradiation Creep in Generation IV Reactors

    Nuclear Energy Research Initiative Program (NERI) Quarterly Progress Report - New Design Equations for Swelling and Irradiation Creep in Generation IV Reactors

    Published 2003
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  20. 120
    Nuclear Energy Research Initiative Program (NERI) Quarterly Progress Report - New Design Equations for Swelling and Irradiation Creep in Generation IV Reactors

    Nuclear Energy Research Initiative Program (NERI) Quarterly Progress Report - New Design Equations for Swelling and Irradiation Creep in Generation IV Reactors

    Published 2003
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