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  1. No Access

    Chapter and Conference Paper

    Assessing Manufacturability of the Oxide Dispersion Strengthened (ODS) 14YWT Alloy Fuel Cladding Tube Using SolidStir™ Technology

    The 14YWT (Fe–14Cr–3W–0.4Ti–0.3Y2O3 (wt.%)) alloy is a potential candidate material for fabricating and other structural components to be used in next-generation advanced nuclear reactors. Due to inherent limit...

    Shubhrodev Bhowmik, Pranshul Varshney… in Friction Stir Welding and Processing XII (2023)

  2. No Access

    Article

    Interplay Between Grain Boundaries and Radiation Damage

    The need for enhanced radiation-tolerant materials for advanced nuclear energy designs has resulted in a growing number of investigations that have explored the effect of grain boundaries under irradiation. Th...

    Christopher M. Barr, Osman El-Atwani, Djamel Kaoumi, Khalid Hattar in JOM (2019)

  3. Article

    Erratum to: Nanomechanical Characterization of Temperature-Dependent Mechanical Properties of Ion-Irradiated Zirconium with Consideration of Microstructure and Surface Damage

    Jonathan Marsh, Yang Zhang, Devendra Verma, Sudipta Biswas, Aman Haque… in JOM (2015)

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