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[6] ] M. Lloret, M. Quecedo, J.M. Conde, C. Alejano, J.M. Rey, F.J. Fernández, “Results of thermal creep tests on irradiated Zry-2”, Proceedings of the 2012 TopFuel meeting, Manchester, UK, September 2 –6, 2012. [7] George P. Sabol, Journal of ASTM international 2 (2) (2005) (paper ID JAI12942). [8] M.A. Martín-Rengel, Integridad estructural de vainas de combustible nuclear. en condiciones de almacenamiento temporal en seco, PhD Thesis, Universidad Politécnica de Madrid, 2009. ENRESA technical publication 05-2010 (in Spanish). [9] ASTM B811-90 “Standard Specification fo Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding” [10] K. Kese. “Hydride Re-Orientation in Zircaloy and its Effect on the Tensile Properties.” SKI Report 98:32. (1998). [11] NRC Interim Staff Guidance ISG-11. [12] M.C. Billone, T.A. Burtseva and R. Einziger,“Ductile-to-brittle transition temperature for high burnup cladding alloys exposed to simulated drying-storage conditions”, J. Nucl. Mater., Vol. 433, pp 431-448 (2013).