1. V. A. Markelov, Improvement of the Composition and Structure of Zirconium Alloys to Secure the Serviceability of Fuel Elements, Fuel Assemblies and Pressure Pipes in the Cores of Water Cooled Reactors with Increasing Service Life and Fuel Burnup: Dissert. Doct. Techn. Sci., VNIINM, Moscow (2010).
2. D. Pêcheur, A. Giordano, E. Picard, et al., “Effect of elevated lithium on the waterside corrosion of zircaloy-4: experimental and predictive studies,” in: Proc. Techn. Com. Meet. IAEA, Czech Republic, Rez, Oct. 4–8, 1993, pp. 111–130.
3. V. Bouniau, A. Ambard, G. Benier, et al., “A new model to predict the oxidation kinetics of zirconium alloys in PWR,” in: Proc. ASTM 15th Int. Symp. Zirconium in the Nuclear Industry, USA, Oregon (2007) pp. 405–430.
4. A. Yilmazbayhan, A. T. Motta, R. J. Comstock, et al., “Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: relation to corrosion rate,” J. Nucl. Mater., 324, 6–22 (2004).
5. A. Garde, W. Slagle, D. Mitchell, et al., “Hydrogen pick-up fraction for zirloTM cladding corrosion and resulting impact on the cladding integrity,” in: Proc. Water Reactor Fuel Performance Meeting, France, Paris, Sept. 6–10, 2009, pp. 902–913.