Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings

Abstract Surface-modified zirconium (Zr)-based alloys, mainly by fabricating protective coatings, are being developed and evaluated as accident-tolerant fuel (ATF) claddings, aiming to improve fuel reliability and safety during normal operations, anticipated operational occurrences, and accident scenarios in water-cooled reactors. In this overview, the performance of Zr alloy claddings under normal and accident conditions is first briefly summarized. In evaluating previous studies, various coating concepts are highlighted based on coating materials, focusing on their performance in autoclave hydrothermal corrosion tests and high-temperature steam oxidation tests. The challenges for the utilization of coatings, including materials selection, deposition technology, and stability under various situations, are discussed to provide some valuable guidance to future research activities.

[1]  J. C. Brachet,et al.  Hydrogen Content, Preoxidation, and Cooling Scenario Effects on Post-Quench Microstructure and Mechanical Properties of Zircaloy-4 and M5 ® Alloys in LOCA Conditions , 2008 .

[2]  Kenneth A. Rogers,et al.  Fire in the hole : A review of national spent nuclear fuel disposal policy , 2009 .

[3]  P. Xiao,et al.  A study of the zirconium alloy protection by Cr3C2–NiCr coating for nuclear reactor application , 2016 .

[4]  H. Harada,et al.  Chromium and chromium-based alloys: Problems and possibilities for high-temperature service , 2004 .

[5]  A. Majumdar,et al.  Opportunities and challenges for a sustainable energy future , 2012, Nature.

[6]  Michel W. Barsoum,et al.  The MN+1AXN phases: A new class of solids , 2000 .

[7]  C.R.F. Azevedo,et al.  Selection of fuel cladding material for nuclear fission reactors , 2011 .

[8]  Jung-Hwan Park,et al.  High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings , 2015 .

[9]  Frédéric Schuster,et al.  ASSESSMENT AT CEA OF COATED NUCLEAR FUEL CLADDING FOR LWRS WITH INCREASED MARGINS IN LOCA AND BEYOND LOCA CONDITIONS , 2013 .

[10]  Hongbin Zhang,et al.  Superior corrosion resistance properties of TiN-based coatings on Zircaloy tubes in supercritical water , 2014 .

[11]  Jung-Hwan Park,et al.  Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions , 2016 .

[12]  W. Cook,et al.  Pourbaix diagrams for chromium, aluminum and titanium extended to high-subcritical and low-supercritical conditions , 2012 .

[13]  Konings Rudy,et al.  Corrosion of Zirconium Alloys , 1964 .

[14]  G. Schanz,et al.  Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations: Part I. Experimental database and basic modeling☆ , 2004 .

[15]  Y. Jung,et al.  HIGH-TEMPERATURE OXIDATION BEHAVIOR OF CR-COATED ZIRCONIUM ALLOY , 2013 .

[16]  R. Baney,et al.  The effect of Zircaloy-4 substrate surface condition on the adhesion strength and corrosion of SiC coatings , 2005 .

[17]  W. Cook,et al.  Pourbaix diagrams for the nickel-water system extended to high-subcritical and low-supercritical conditions , 2012 .

[18]  Martin Steinbrück,et al.  High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys , 2010 .

[19]  Walter G. Luscher,et al.  SURFACE MODIFICATION OF ZIRCALOY-4 SUBSTRATES WITH NICKEL ZIRCONIUM INTERMETALLICS , 2013 .

[20]  S. Ulrich,et al.  Synthesis and characterization of Ti2AlC coatings by magnetron sputtering from three elemental targets and ex-situ annealing , 2017 .

[21]  Van Uffelen Paul,et al.  Analysis of Reactor Fuel Rod Behaviour , 2010 .

[22]  A. Motta,et al.  Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding , 2016 .

[23]  Martin Steinbrück,et al.  Oxidation of Advanced Zirconium Cladding Alloys in Steam at Temperatures in the Range of 600–1200 °C , 2011 .

[24]  Richard J. Day,et al.  Oxidation protection for carbon fibre composites , 1996, Journal of Materials Science.

[25]  Seungjoon Kim,et al.  Fretting damage of TiN coated zircaloy-4 tube , 2001 .

[26]  F. Rizzo,et al.  The oxidation behaviour of metals and alloys at high temperatures in atmospheres containing water vapour: A review , 2008 .

[27]  Arthur T. Motta,et al.  Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding , 2015 .

[28]  Tomasz Kozlowski,et al.  Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions , 2015 .

[29]  Hugh O. Pierson,et al.  Handbook of Refractory Carbides and Nitrides: Properties, Characteristics, Processing and Applications , 1996 .

[30]  Yongsong Xie,et al.  Deposition, characterization and performance evaluation of ceramic coatings on metallic substrates for supercritical water-cooled reactors , 2011 .

[31]  James P. Carr,et al.  Investigations of Aluminum-Doped Self-Healing Zircaloy Surfaces in Context of Accident-Tolerant Fuel Cladding Research , 2016, Journal of Materials Engineering and Performance.

[32]  G. Was,et al.  Performance of iron-chromium-aluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions , 2016 .

[33]  I. Bhamji,et al.  Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO™ fuel cladding using a modified shear-lag model approach , 2015 .

[34]  Steven J. Zinkle,et al.  Accident tolerant fuels for LWRs: A perspective , 2014 .

[35]  D. Young High Temperature Oxidation and Corrosion of Metals , 2008 .

[36]  V. Ovcharenko,et al.  HIGH-TEMPERATURE AIR OXIDATION OF E110 AND Zr-1Nb ALLOYS CLADDINGS WITH COATINGS , 2014 .

[37]  V. Ovcharenko,et al.  Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air , 2015 .

[38]  J. Macák,et al.  Thin polycrystalline diamond films protecting zirconium alloys surfaces: From technology to layer analysis and application in nuclear facilities , 2015 .

[39]  Donald R. Olander,et al.  Oxidation of Zircaloy by steam , 1991 .

[40]  Steven J. Zinkle,et al.  Materials Challenges in Nuclear Energy , 2013 .

[41]  M. Fratoni,et al.  Neutronic evaluation of coating and cladding materials for accident tolerant fuels , 2016 .

[42]  J. R. Conrad,et al.  Plasma source ion-implantation technique for surface modification of materials , 1987 .

[43]  K. Daub,et al.  Investigation of the impact of coatings on corrosion and hydrogen uptake of Zircaloy-4 , 2015 .

[44]  A Soniak,et al.  Irradiation Creep and Growth Behavior, and Microstructural Evolution of Advanced Zr-Base Alloys , 2000 .

[45]  D. A. Roberts Magnetron Sputtering and Corrosion of Ti-Al-C and Cr-Al-C coatings for Zr-alloy Nuclear Fuel Cladding , 2016 .

[46]  E. Dinjus,et al.  Factors controlling corrosion in high-temperature aqueous solutions: a contribution to the dissociation and solubility data influencing corrosion processes , 1999 .

[47]  Steven J. Zinkle,et al.  Advanced Oxidation Resistant Iron-Based Alloys for LWR Fuel Cladding , 2014 .

[48]  M. Anderson,et al.  Oxidation of plasma surface modified zirconium alloy in pressurized high temperature water , 2007 .

[49]  Kurt A. Terrani,et al.  Silicon Carbide Oxidation in Steam up to 2 MPa , 2014 .

[50]  Y. Sibamoto,et al.  Insights from review and analysis of the Fukushima Dai-ichi accident , 2012 .

[51]  A. Motta,et al.  MULTILAYER CERAMIC COATING FOR CORROSION (C3) RESISTANCE OF NUCLEAR FUEL CLADDING , 2015 .

[52]  Sang-Yun Park,et al.  Out-of-pile and In-pile Perfomance of Advanded Zirconium Alloys (HANA) for High Burn-up Fuel , 2006 .

[53]  C. Vega,et al.  Phase diagram of water from computer simulation. , 2004, Physical review letters.

[54]  X. Bai,et al.  Influence of aluminum ions implanted on oxidation behavior of ZIRLO alloy at 500 °C , 2006 .

[55]  P. Ho,et al.  Theoretical Study of the Thermochemistry of Molecules in the SiO-H System , 2001 .

[56]  L. Shao,et al.  Nanosized polycrystalline diamond cladding for surface protection of zirconium nuclear fuel tubes , 2014 .

[57]  S. W. Sharkawy,et al.  Pyrolytic carbon coating of Zircaloy-4 tubes at relatively low temperatures , 1997 .

[58]  S. Bragg‐Sitton Development of advanced accident-tolerant fuels for commercial LWRs , 2014 .

[59]  S. H. Jury,et al.  Zirconium metal-water oxidation kinetics. IV. Reaction rate studies. [BWR:PWR] , 1977 .

[60]  J. Park,et al.  Application of Coating Technology on Zirconium-Based Alloy to Decrease High-Temperature Oxidation , 2015 .

[61]  C. Ziebert,et al.  Concepts for the design of advanced nanoscale PVD multilayer protective thin films , 2009 .

[62]  S. Hogmark,et al.  Multilayer coatings as corrosion protection of Zircaloy , 1996 .

[63]  M. Barsoum,et al.  A Critical Review of the Oxidation of Ti2AlC, Ti3AlC2 and Cr2AlC in Air , 2013 .

[64]  E. Jordan,et al.  Thermal Barrier Coatings for Gas-Turbine Engine Applications , 2002, Science.

[65]  Kurt A. Terrani,et al.  Uniform corrosion of FeCrAl alloys in LWR coolant environments , 2016 .

[66]  Kurt A. Terrani,et al.  Protection of Zirconium by Alumina- and Chromia-Forming Iron Alloys under High-Temperature Steam Exposure , 2013 .

[67]  K. Sridharan,et al.  Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate , 2016 .

[68]  Yang-Hyun Koo,et al.  Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating , 2015 .

[69]  K. Sridharan,et al.  Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding , 2015 .