You are being redirected because this document is part of your ASTM Compass® subscription.
    This document is part of your ASTM Compass® subscription.

    STP1543

    Microstructure and Properties of a Three-Layer Nuclear Fuel Cladding Prototype Containing Erbium as a Neutronic Burnable Poison

    Published: 2014


      Format Pages Price  
    PDF (7.3M) 41 $25   ADD TO CART
    Complete Source PDF (120M) 1177 $265   ADD TO CART

    Cite this document

    X Add email address send
    X
      .RIS For RefWorks, EndNote, ProCite, Reference Manager, Zoteo, and many others.   .DOCX For Microsoft Word


    Abstract

    To increase cycle length and/or fuel burnup, several theoretical and experimental studies have been performed at CEA. Among them, prospective neutronic calculations have shown that the addition of a few weight percents of erbium into the cladding materials could be a promising alternative to the introduction of the neutronic poison directly into the nuclear fuel pellets. Thus, fabrication of homogeneous Zr-Er alloys has been assessed, at least up to 10 wt. % of erbium and, based on the as-received mechanical properties, an optimum erbium concentration ranging from 3 to 6 wt. % has been derived. However, because of the high-oxygen thermodynamic affinity of erbium, thermal treatments have to be controlled during the fabrication route to limit Er2O3 precipitation and coarsening, which may have detrimental effects on the ductility/toughness of Zr-Er alloys. In parallel, to get more fundamental insights into the underlying phase diagrams, thermodynamic studies have been devoted to experimental assessment and modeling of the Zr-Er-(H-O) system. Because of the detrimental influence of erbium on the corrosion resistance, a three-layer sandwich clad prototype has been developed using corrosion-resistant inner/outer Zr-1Nb layers to protect the intermediate Zr-Er layer from direct water exposure. Compared to a reference Zr-1Nb(O) alloy that has been subjected to the same fabrication route, the three-layer clad prototype shows limited decrease in ductility because of pre-hydriding or after high-temperature steam oxidation e.g., in the case of a loss-of-coolant accident). Moreover, the studies performed so far have shown a spectacular hydride trapping capacity of the intermediate Zr-Er layer both for hydrogen coming from nominal outer corrosion or because of massive secondary hydriding in case of the direct access of water to the Zr-Er intermediate layer. Using μ-ERDA (elastic recoil detection analysis) measurements, detailed studies of the hydrogen spatial redistribution upon thermal cycling has been done. A simple model has been successfully used to characterize the cooling rate influence on the through-wall clad thickness partitioning of hydrogen/hydrides between the three layers, after cooling from a temperature corresponding to full dissolution of hydrides.

    Keywords:

    erbium, neutronic burnable poison, zirconium-erbium-hydrogen-oxygen phase diagrams, CALPHAD, Thermocalc, Zircobase, hydrogen trapping, three-layer-clad, μ-ERDA


    Author Information:

    Brachet, J. C.
    CEA-DEN, Dept. for Nuclear Materials, Section for Applied Metallurgy Research, CEA-Saclay, Gif-sur-Yvette Cedex,

    Olier, P.
    CEA-DEN, Dept. for Nuclear Materials, Section for Applied Metallurgy Research, CEA-Saclay, Gif-sur-Yvette Cedex,

    Vandenberghe, V.
    CEA-DEN, Dept. for Nuclear Materials, Section for Applied Metallurgy Research, CEA-Saclay, Gif-sur-Yvette Cedex,

    Doriot, S.
    CEA-DEN, Dept. for Nuclear Materials, Section for Applied Metallurgy Research, CEA-Saclay, Gif-sur-Yvette Cedex,

    Urvoy, S.
    CEA-DEN, Dept. for Nuclear Materials, Section for Applied Metallurgy Research, CEA-Saclay, Gif-sur-Yvette Cedex,

    Hamon, D.
    CEA-DEN, Dept. for Nuclear Materials, Section for Applied Metallurgy Research, CEA-Saclay, Gif-sur-Yvette Cedex,

    Guilbert, T.
    CEA-DEN, Dept. for Nuclear Materials, Section for Applied Metallurgy Research, CEA-Saclay, Gif-sur-Yvette Cedex,

    Mascaro, A.
    CEA-DEN, Dept. for Nuclear Materials, Section for Applied Metallurgy Research, CEA-Saclay, Gif-sur-Yvette Cedex,

    Jourdan, J.
    CEA-DEN, Dept. for Nuclear Materials, Section for Applied Metallurgy Research, CEA-Saclay, Gif-sur-Yvette Cedex,

    Toffolon-Masclet, C.
    CEA-DEN, Dept. for Nuclear Materials, Section for Applied Metallurgy Research, CEA-Saclay, Gif-sur-Yvette Cedex,

    Tupin, M.
    CEA-DEN, Dept. for Nuclear Materials, Section for Research on Irradiated Materials, CEA-Saclay, Gif-sur-Yvette Cedex,

    Bourdiliau, B.
    CEA-DEN, Dept. for Nuclear Materials, Section for Research on Irradiated Materials, CEA-Saclay, Gif-sur-Yvette Cedex,

    Raepsaet, C.
    CEA-DSM, IRAMIS/SIS2M/LEEL, CEA-Saclay, Gif-sur-Yvette Cedex,

    Joubert, J. M.
    Chimie Métallurgique des Terres Rares, ICMPE, CNRS, Université Paris-Est, Thiais,

    Aubin, J. L.
    AREVA-CEZUS, Paimboeuf,


    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP154320130053