TY - JOUR AB - Zirconium-based alloys are used in water-cooled nuclear reactors for both nuclear fuel cladding and structural components. Under this harsh environment, the main factor limiting the service life of zirconium cladding, and hence fuel burn-up efficiency, is water corrosion. This oxidation process has recently been linked to the presence of a sub-oxide phase with well-defined composition but unknown structure at the metal–oxide interface. In this paper, the combination of first-principles materials modeling and high-resolution electron microscopy is used to identify the structure of this sub-oxide phase, bringing us a step closer to developing strategies to mitigate aqueous oxidation in Zr alloys and prolong the operational lifetime of commercial fuel cladding alloys. AU - Nicholls,RJ AU - Ni,N AU - Lozano-Perez,S AU - London,A AU - McComb,DW AU - Nellist,PD AU - Grovenor,CRM AU - Pickard,CJ AU - Yates,JR DO - 10.1002/adem.201400133 EP - 215 PY - 2014/// SN - 1527-2648 SP - 211 TI - Crystal Structure of the ZrO Phase at Zirconium/Zirconium Oxide Interfaces T2 - Advanced Engineering Materials UR - http://dx.doi.org/10.1002/adem.201400133 UR - http://hdl.handle.net/10044/1/40605 VL - 17 ER -