Hydrogen in Zirconium Alloys: a Review
Journal of Nuclear Materials 518 (2019) 440e460 Contents lists available at ScienceDirect Journal of Nuclear Materials journal homepage: www.elsevier.com/locate/jnucmat Hydrogen in zirconium alloys: A review * Arthur T. Motta a, , Laurent Capolungo b, Long-Qing Chen c, Mahmut Nedim Cinbiz d, Mark R. Daymond e, Donald A. Koss c, Evrard Lacroix a, Giovanni Pastore f, Pierre-Clement A. Simon a, Michael R. Tonks g, Brian D. Wirth h, Mohammed A. Zikry i a Department of Mechanical and Nuclear Engineering, 138 Reber Bldg, Penn State University, University Park, PA, 16802, USA b Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM, 87545, USA c Department of Materials Science and Engineering, The Pennsylvania State University, University Park, PA, 16802-5006, USA d Reactor and Nuclear Systems Division, Nuclear Fuel Materials Group, Oak Ridge National Laboratory, Oak Ridge, TN, 37831, USA e Dept. of Mechanical and Materials Engineering, Queen's University, Kingston, Ontario, K7L 3N6, Canada f Idaho National Laboratory, Fuel Modeling and Simulation Department, Idaho Falls, ID, 83415, USA g Department of Materials Science and Engineering, University of Florida, Gainesville, FL, 32611, USA h Department of Nuclear Engineering, University of Tennessee, Knoxville, TN, 37996-1410, USA i Dept. of Mechanical and Aerospace Engineering, North Carolina State University, Raleigh, NC, 27695-7910, USA article info abstract Article history: Hydrogen absorbed into zirconium alloy nuclear fuel cladding as a result of the waterside corrosion Received 4 January 2019 reaction can affect the properties of nuclear fuel, principally through the precipitation of brittle hydride Received in revised form particles.
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