STP1423

    The Behavior of Intermetallic Precipitates in Highly Irradiated BWR LTP Cladding

    Published: Jan 2002


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    Abstract

    Advanced Zry-2 cladding materials exhibiting good corrosion behavior are a prerequisite for extending BWR operation towards high burnup. To assess the burnup potential of Zry-2, the behavior of the intermetallic second-phase precipitates was analyzed as a function of fluence and compared with the in-reactor corrosion behavior. Various Zry-2 cladding samples with particle densities between 3 and 13 mm-2 with an average particle diameter of 50 to 80 nm and irradiation times of up to 2400 EFPD, equivalent to neutron fluences of up to 1 ∙ 1022 cm-2 (En > 1 MeV), were analyzed by TEM/SEM. The measurements showed a significant decrease in the particle density within the first cycle of irradiation followed by a slow decrease up to high fluences. At the highest fluences, the precipitate structure underwent deterioration combined with a markedly reduced number density. However, about 1 to 2% new precipitates of the Zr3Fe-type were formed during irradiation.

    Metallographic examinations of BWR fuel rods showed both nodular and uniform corrosion. Up to a local burnup of 65 MWd/kgU no change of the corrosion kinetics and no acceleration of corrosion was found.

    Keywords:

    zirconium alloys, precipitates, precipitate type, precipitate size, precipitate distribution, precipitate dissolution, neutron irradiation, nodular corrosion, uniform corrosion, nuclear application


    Author Information:

    Goll, W
    Framatome ANP GmbH, Erlangen,

    Ray, L
    European Commission Joint Research Centre, Institute for Transuranium Elements, Karlsruhe,


    Paper ID: STP11384S

    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP11384S


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