STP1505

    In-Pile Criteria for the Initiation of Massive Hydriding of Zr in Steam-Hydrogen Environment

    Published: Jan 2009


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    Abstract

    It is shown that irradiation of oxide film on the surface of zirconium alloy by fission fragments may promote the breakdown of oxide protective properties and lead to massive hydriding of zirconium in a steam-hydrogen environment far beyond the condition of “oxygen starvation.” Massive hydriding of zirconium claddings may cause severe secondary degradation of failed fuel rods in commercial nuclear reactors. The effect of irradiation is concerned with two factors. The first one is radiolysis of steam-hydrogen mixture and chemical interaction of highly reactive radicals with the oxide surface. The second factor is intense generation of radiation-induced defects in crystal lattice of ZrO2 which enhance the rate of oxide reduction. A model is proposed for assessment of the threshold conditions for the onset of massive hydriding depending on composition of steam-hydrogen mixture and irradiation dose rate.

    Keywords:

    zirconium alloys, massive hydriding, defective fuel rods, secondary failures, irradiation, fission fragments, steam-hydrogen mixtures, radiolysis, radiation-induced defects


    Author Information:

    Evdokimov, I. A.
    Head of Reactor Materials Laboratory and Head of the Nuclear Safety Department, State Research Center of the Russian Federation, Troitsk Institute for Innovation and Fusion Research (SRC RF TRINITI), Troitsk, Moscow reg.

    Likhanskii, V. V.
    Head of Reactor Materials Laboratory and Head of the Nuclear Safety Department, State Research Center of the Russian Federation, Troitsk Institute for Innovation and Fusion Research (SRC RF TRINITI), Troitsk, Moscow reg.


    Paper ID: STP48137S

    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP48137S


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