F. Garzarolli, Y. Broy, and R. A. Busch, Comparison of the Long-Time Corrosion Behaviour of Certain Zr Alloys in PWR, BWR and Laboratory Tests, Zirconium in the Nuclear Industry: 11th International Symposium, 1996.

M. Blat, Contribution to a Better Understanding of the Detrimental Role of Hydrogen on the Corrosion Rate of Zircaloy-4 Cladding Materials, Zirconium in the Nuclear Industry: 12th International Symposium, 2000.

Y. S. Kim, K. S. Rheen, and D. K. Min, Phenomenological Study of In-Reactor Corrosion of Zirconium Alloys by Hydrides, Zirconium in the Nuclear Industry: 10th International Symposium, 1994.

A. M. Garde, Enhancement of Aqueous Corrosion of Zircaloy-4 Due to Hydride Precipitation at the Metal/Oxide Interface, Zirconium in the Nuclear Industry: 9th International Symposium, 1991.

X. Iltis, F. Lefebvre, and C. Lemaignan, Microstructure Evolution and Iron Redistribution in Zircaloy Oxide Layers: Comparative Effets of Neutron Irradiation Flux and Irradiation Damages, Zirconium in the Nuclear Industry: 11th International Symposium, 1996.

C. Lemaignan, Physical Phenomena Concerning Corrosion Under Irradiation of Zr Alloys, Zirconium in the Nuclear Industry: 13th International Symposium, 2002.

D. L. Douglass, The Metallurgy of Zirconium, International Atomic Energy Agency, 1971.

F. Lefebvre and C. Lemaignan, Irradiation Effects on Corrosion of Zirconijm Alloys Claddings, Journal of Nuclear Materials, vol.248, pp.268-274, 1997.

D. Pêcheur, Precipitate evolution in the Zircaloy-4 oxide layer, Journal of Nuclear Materials, 1992, vol.189, issue.3, pp.318-332

M. Tupin, Mechanism of corrosion of zirconium hydride and impact of precipitated hydrides on the Zircaloy-4 corrosion behaviour, Corrosion Science, vol.98, pp.478-493, 2015.

C. Bisor-melloul, Compréhension des mécanismes de prise d'hydrogène des alliages de zirconium en situation de corrosion en conditions REP -Impact des hydrures sur la corrosion du Zircaloy-4, Department of Nuclear Materials -CEA2010

Y. Dali, Corrosion kinetics under high pressure of steam of pure zirconium and zirconium alloys followed by in situ thermogravimetry, Journal of Nuclear Materials, vol.426, pp.148-159, 2012.
URL : https://hal.archives-ouvertes.fr/hal-00747505

C. Gibert-mougel, Phase transformation of polycrystalline zirconiuam induced by swift heavy ion irradiation, Journal of Nuclear Materials, vol.295, pp.121-125, 2001.

A. Yilmazbayhan, Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: relation to corrosion rate, Journal of Nuclear Materials, vol.324, pp.6-22, 2004.

S. Doriot, Microstructural Stability of M5 Alloy Irradiated up to High Neutron Fluences, Zirconium in the Nuclear Industry: 14th International Symposium, 2005.

X. T. Zu, Effet of proton and Ne irradiation on the microstructure of Zircaloy-4. Philosophical Magazine, vol.85, pp.649-659, 2012.

R. C. Garvie and P. S. Nicholson, Phase analysis in zirconia systems, Journal of the American Ceramic Society, vol.55, issue.6, pp.303-305, 1972.

A. T. Motta, Microstructure and growth mechanism of oxide layers formed on Zr alloys studied with micro-beam synchrotron radiation, Zirconium in the Nuclear Industry: 14th International Symposium, 2005.

J. L. Bechade, Studies of Zirconium Alloy Oxide Layers Using Synchrotron Radiation, Materials Science Forum, vol.347, issue.1, pp.471-476, 2000.

P. Bossis, Multi-Scale Characterization of the Metal-Oxide Interface of Zirconium Alloys, Zirconium in the Nuclear Industry: 12th International Symposium, 2000.

N. Petigny, In situ XRD analysis of the oxide layers formed by oxidation at 743 K on Zircaloy-4 and Zr-1NbO, Journal of Nuclear Materials, vol.280, p.318, 2000.

H. G. Kim, T. H. Kim, and Y. H. Jeong, Oxidation characteristics of basal (0002) plane and prism (1120) plane in HCP Zr, Journal of Nuclear Materials, p.306, 2002.

V. Vrtlikova, 24. The Powder Diffraction File, International topical meeting on LWR fuel performance. 2000. Park City, 2006.

B. D. Cullity, Elements of X-ray Diffraction

R. Verlet, Influence of light ion irradiation of the oxide layer on the oxidation rate of Zircaloy-4, Corrosion Science, vol.98, pp.327-338, 2015.
URL : https://hal.archives-ouvertes.fr/emse-01495043

M. Raza, Oxygen vacancy stabilized zirconia (OVSZ); a joint experimental and theoretical study, Scripta Materialia, vol.124, pp.26-29, 2016.

J. Thomazet, Fragema zirconium alloy corrosion behaviour and development. in Fondamental Aspects of Corrosion on Zirconium Base Alloys in Water Reactor Environments, 1990.