Microstructural analysis of as-processed U-10 wt.%Mo monolithic fuel plate in AA6061 matrix with Zr diffusion barrier

    Authors

    E. Perez; B. Yao; D. D. Keiser;Y. H. Sohn

    Comments

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    Abbreviated Journal Title

    J. Nucl. Mater.

    Keywords

    DISPERSION FUEL; HIGH-DENSITY; URANIUM; ZIRCONIUM; SYSTEM; INTERDIFFUSION; ALLOYS; PHASE; MOLYBDENUM; ALUMINUM; Materials Science, Multidisciplinary; Nuclear Science & Technology; Mining & Mineral Processing

    Abstract

    For higher U-loading in low-enriched U-10 wt.%Mo fuels, monolithic fuel plate clad in AA6061 is being developed as a part of Reduced Enrichment for Research and Test Reactor (RERTR) program. This paper reports the first characterization results from a monolithic U-10 wt.%Mo fuel plate with a Zr diffusion barrier that was fabricated as part of a plate fabrication campaign for irradiation testing in the Advanced Test Reactor (ATR). Both scanning and transmission electron microscopy (SEM and TEM) were employed for analysis. At the interface between the Zr barrier and U-10 wt.%Mo, going from Zr to U(Mo), UZr(2), gamma-UZr, Zr solid-solution and Mo(2)Zr phases were observed. The interface between AA6061 cladding and Zr barrier plate consisted of four layers, going from Al to Zr, (Al, Si)(2)Zr, (Al, Si)Zr(3) (Al, Si)(3)Zr, and AlSi(4)Zr(5). Irradiation behavior of these intermetallic phases is discussed based on their constituents. Characterization of as-fabricated phase constituents and microstructure would help understand the irradiation behavior of these fuel plates, interpret post-irradiation examination, and optimize the processing parameters of monolithic fuel system. (C) 2010 Elsevier B.V. All rights reserved.

    Journal Title

    Journal of Nuclear Materials

    Volume

    402

    Issue/Number

    1

    Publication Date

    1-1-2010

    Document Type

    Article

    Language

    English

    First Page

    8

    Last Page

    14

    WOS Identifier

    WOS:000279612500002

    ISSN

    0022-3115

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