Zirconium Alloys in Nuclear Applications

@article{Lemaignan2006ZirconiumAI,
  title={Zirconium Alloys in Nuclear Applications},
  author={C. Lemaignan and A. Motta},
  journal={Materials Science and Technology},
  year={2006}
}
  • C. Lemaignan, A. Motta
  • Published 2006
  • Materials Science
  • Materials Science and Technology
    • View via Publisher
    mne.psu.edu
    106 Citations
    Highly Influential Citations
    7
    Background Citations
    35
    Methods Citations
    7
    106 Citations
    Citation Type

    Citation Type

    Direct measurement of hydrogen diffusivity and solubility limits in Zircaloy 2 (formula unit of ZrH0.0155) using incoherent quasi-elastic neutron scattering
    • 1
    • Highly Influenced
    Material development for India’s nuclear power programme
    • 11
    • Highly Influenced
    Evolution of the Oxide Microstructure and Oxide Growth Induced Residual Strains During Waterside Corrosion of Zirconium Alloys
    • 1
    • Highly Influenced
    An Electrolytic Method to Form Zirconium Hydride Phases in Zirconium Alloys with Morphologies Similar to Hydrides Formed in Used Nuclear Fuel
    • 1
    • Highly Influenced
    Comportement en fluage à haute température dans le domaine biphasé (α + β) de l'alliage M5®
    • 5
    • Highly Influenced
    Investigation of the mechanical behavior of rim/blister structure hydride phases in Zircaloy-4 by utilizing high energy synchrotron X-ray diffraction
    • Highly Influenced
    In-situ phase studies of the Zr-H system
    • Highly Influenced
    XANES ANALYSIS OF IRON IN ZIRCALOY-4 OXIDES FORMED AT DIFFERENT TEMPERATURES STUDIED WITH MICROBEAM SYNCHROTRON RADIATION
    • 3
    • PDF
    Experimental study, first-principles calculations and thermodynamic modelling of the Cr–Fe–Nb–Sn–Zr quinary system for application as cladding materials in nuclear reactors.
    Effets de l’oxygène et de l’hydrogène sur la microstructure et le comportement mécanique d’alliages de zirconium après incursion à haute température

    References

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    Impact of β− radiolysis and transient products on irradiation-enhanced corrosion of zirconium alloys
    • 18
    Influence of texture on iodine-induced stress corrosion cracking of Zircaloy-4 cladding tubes
    • 40
    Mechanisms of Radiation Induced Amorphization
    • 8
    Precipitate evolution in the Zircaloy-4 oxide layer
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    • PDF
    Production bias due to clustering of point defects in irradiation-induced cascades
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    Fe-enhancement of self-diffusion in α-Zr
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    Kobe, Japan: ASTM-STP 1132
    • 9th Int. Conf. Zr Nucl. Ind.,
    • 1991
    Kobe, Japan: ASTM-STP 1132
    • 9th Int. Symp. Zr Nucl. Ind., Nov
    • 1991