STP1529: Hydrogen Solubility and Microstructural Changes in Zircaloy-4 Due to Neutron Irradiation

    Vizcaíno, P.
    Centro Atómico Ezeiza (CAE), Comisión Nacional de Energía Atómica (CNEA), Buenos Aires,

    Carrera del Investigador del Consejo Nacional de Ciencia y Técnica (CONICET), Buenos Aires,

    LMFAE, CAE, CNEA, Buenos Aires,

    Flores, A. V.
    LMFAE, CAE, CNEA, Buenos Aires,

    Bozzano, P. B.
    UAM, CAC, CNEA, Buenos Aires,

    Banchik, A. D.
    LMFAE, CAE, CNEA, Buenos Aires,

    Versaci, R. A.
    UAM, CAC, CNEA, Buenos Aires,

    Ríos, R. O.
    LMFAE, CAE, CNEA, Buenos Aires,

    Pages: 30    Published: Apr 2012


    Abstract

    The present work deals with two essential degradation mechanisms of zirconium alloys: Hydrogen behavior and microstructural transformations due to neutron irradiation. The studies were carried out by using samples taken from Zircaloy-4 components, which remained for 14 years in the Atucha I pressurized heavy water reactor, accumulating neutron fluences of up to 1022 neutrons/cm2. A hydrogen/deuterium solubility increase was observed in both dissolution and precipitation processes. With the aim to follow this evolution with radiation damage recovery, the irradiated samples were annealed for different periods at 350 and 400°C in a differential scanning calorimeter (DSC). These temperatures were chosen to reproduce those reached by spent fuels in the early stages of the dry storage (DS). Between intervals, the terminal solid solubility temperatures in dissolution (TTSSd) and in precipitation (TTSSp) were determined. They were also determined after additional annealing at 500 and 600°C, trying to simulate long periods at DS. The hydride morphology and the metallurgical state of the Zr(Fe, Cr)2 second-phase particles (SPPs) were followed between annealing by optical microscopy, analytical electron microscopy, synchrotron light X-ray diffraction4 (SXRD), and DSC. As a brief summary, we found from the first to the last run of the annealing sequence an increase of 55°C in TTSSd and 40°C in TTSSp on average. The optical and transmission electron microscopies (TEM) indicate that in the material in the irradiated condition, exists a hydride size distribution of four orders of magnitude, from 10 nm to 100 μm, but biased to sizes smaller than 5 μm. A complete amorphisation of the SPPs was observed in high fluence samples by TEM and SXRD. Similar TEM observations made in irradiated samples annealed above 400°C show a re-precipitation process of nano-SPPs forming clusters. The re-precipitation is affected by kinetics: The SPPs crystallization temperature, Tc, rises from 450 to 500°C as the heating rate increases from 5 to 20°C/min. The measured heat of crystallization was 27.3±2.1 kJ/mol (Fe + Cr).

    Keywords:

    Zircaloy-4, irradiation, hydrogen, SPPs, AEM, DSC


    Paper ID: STP152920120030

    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP152920120030


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