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  1. 81
    Mechanistic Studies of Zircaloy Nodular Corrosion /
    by Adamson, RB, Cheng, B.
    Published 1987

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    Book
  2. 82
    Mechanistic Modeling of Zircaloy Deformation and Fracture in Fuel Element Analysis /
    by Nichols, FA
    Published 1987

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    Book
  3. 83
    Accelerated Irradiation Growth of Zirconium Alloys /
    by Griffiths, M., Fidleris, V., Gilbert, RW
    Published 1989

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    Book
  4. 84
    A Laboratory Method to Predict Hydriding Properties of Zirconium Alloys Under Irradiation /

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    Book
  5. 85
    Applications of Crystallographic Textures of Zirconium Alloys in the Nuclear Industry /
    by Murty, KL
    Published 1989

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    Book
  6. 86
    Prevention of Delayed Hydride Cracking in Zirconium Alloys /
    by Ambler, JFR, Cheadle, BA, Coleman, CE
    Published 1987

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    Book
  7. 87
    Thoughts on the Needed Focal Areas in the Research and Understanding of In-Reactor Corrosion, Hydrogen Absorption, and Hydrogen Migration in Zirconium Alloys /
    by Kammenzind, Bruce F.
    Published 2021

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    Book
  8. 88
    Zirconium in the nuclear industry
    Published 1994

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    Conference Proceeding Book
  9. 89
    Zirconium in the nuclear industry
    Published 2005

    This item is not available through BorrowDirect. Please contact your institution’s interlibrary loan office for further assistance.
    Conference Proceeding Book
  10. 90
    Zirconium in the nuclear industry
    Published 1996

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    Conference Proceeding Book
  11. 91
    Out-of-Pile Experiments on the High-Temperature Behavior of Zircaloy-4 Clad Fuel Rods /
    by Hagen, S.
    Published 1984

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    Book
  12. 92
    Characterization of ZrO2 Films Formed In-Reactor and Ex-Reactor to Study the Factors Contributing to the In-Reactor Waterside Corrosion of Zircaloy /

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    Book
  13. 93
    Tube-Burst Response of Irradiated Zircaloy Spent-Fuel Cladding /
    by Bauer, AA, Gallagher, WJ, Lowry, LM
    Published 1979

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    Book
  14. 94
    Influence of Iodine on the Strain and Rupture Behavior of Zircaloy-4 Cladding Tubes at High Temperatures /
    by Hofmann, Peter, Dr. rer. oec
    Published 1979

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    Book
  15. 95
    Further Evidence of Zircaloy Corrosion in Fuel Elements Irradiated in a Steam Generating Heavy Water Reactor /

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    Book
  16. 96
    Embrittlement of Zircaloy-Clad Fuel Rods Irradiated Under Film Boiling Conditions /

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    Book
  17. 97
    Effect of Material and Environmental Variables on Localized Corrosion of Zirconium Alloys /
    by Lunde, L., Videm, K.
    Published 1979

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    Book
  18. 98
    Studies on Zircaloy Fuel Clad Ballooning in a Loss-of-Coolant Accident-Results of Burst Tests with Indirectly Heated Fuel Rod Simulators /
    by Erbacher, F., Neitzel, HJ, Wiehr, K.
    Published 1979

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    Book
  19. 99
    Burst Testing of Zircaloy Cladding from Irradiated Pickering-Type Fuel Bundles /
    by Hardy, DG
    Published 1973

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    Book
  20. 100
    Irradiation Response of the Ordered Phase Zr3Al /

    This item is not available through BorrowDirect. Please contact your institution’s interlibrary loan office for further assistance.
    Conference Proceeding Book
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