Growth kinetics and microstructural evolution during hot isostatic pressing of U-10 wt.% Mo monolithic fuel plate in AA6061 cladding with Zr diffusion barrier

    Authors

    Y. Park; J. Yoo; K. Huang; D. D. Keiser; J. F. Jue; B. Rabin; G. Moore;Y. H. Sohn

    Comments

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    Abbreviated Journal Title

    J. Nucl. Mater.

    Keywords

    U-MO; DISPERSION FUEL; REACTION LAYER; HIGH-DENSITY; SI; MATRIX; ALLOY; Materials Science, Multidisciplinary; Nuclear Science & Technology; Mining & Mineral Processing

    Abstract

    Phase constituents and microstructure changes in RERTR fuel plate assemblies as functions of temperature and duration of hot-isostatic pressing (HIP) during fabrication were examined. The HIP process was carried out as functions of temperature (520, 540, 560 and 580 degrees C for 90 min) and time (45-345 min at 560 degrees C) to bond 6061 Al-alloy to the Zr diffusion barrier that had been co-rolled with U-10 wt.% Mo (U10Mo) fuel monolith prior to the HIP process. Scanning and transmission electron microscopies were employed to examine the phase constituents, microstructure and layer thickness of interaction products from interdiffusion. At the interface between the U10Mo and Zr, following the co-rolling, the UZr2 phase was observed to develop adjacent to Zr, and the alpha-U phase was found between the UZr2 and U10Mo, while the Mo2Zr was found as precipitates mostly within the alpha-U phase. The phase constituents and thickness of the interaction layer at the U10Mo-Zr interface remained unchanged regardless of HIP processing variation. Observable growth due to HIP was only observed for the (Al,Si)(3)Zr phase found at the Zr/AA6061 interface, however, with a large activation energy of 457 +/- 28 kJ/mole. Thus, HIP can be carried to improve the adhesion quality of fuel plate without concern for the excessive growth of the interaction layer, particularly at the U10Mo-Zr interface with the alpha-U, Mo2Zr, and UZr2 phases. (C) 2014 Elsevier B.V. All rights reserved.

    Journal Title

    Journal of Nuclear Materials

    Volume

    447

    Issue/Number

    1-3

    Publication Date

    1-1-2014

    Document Type

    Article

    Language

    English

    First Page

    215

    Last Page

    224

    WOS Identifier

    WOS:000334134600026

    ISSN

    0022-3115

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