5 -Performance and inspection of zirconium alloy fuel bundle components in light water reactors (LWRs)', in Materials Ageing and Degradation in Light Water Reactors, pp.246-283, 2013. ,
Processes going on in Nonfailed Rod during Accident Conditions (LOCA and RIA) Volume II, 2010. ,
Comprehensive presentation of extended Zircaloy-4 steam oxidation results (600-1600 deg. C), 1983. ,
Breakaway phenomenon of Zr-based alloys during a high-temperature oxidation, J. Nucl. Mater, vol.372, issue.2, pp.152-159, 2008. ,
High-temperature steam-oxidation behavior of Zr-1Nb cladding alloy E110', J. Nucl. Mater, vol.393, issue.3, pp.433-448, 2009. ,
A study of the breakaway oxidation behavior of zirconium cladding materials, J. Nucl. Mater, vol.418, issue.1, pp.186-197, 2011. ,
Cladding embrittlement during postulated loss-of-coolant accidents, 2008. ,
Oxidation of Advanced Zirconium Cladding Alloys in Steam at Temperatures in the Range of 600-1200 °C, Oxid. Met, vol.76, issue.3, pp.215-232, 2011. ,
Influence of Long Service Exposures on the Thermal-Mechanical Behavior of Zy-4 and M5 TM Alloys in LOCA Conditions, Zirconium in the Nuclear Industry: Fourteenth International Symposium, 2005. ,
Influence of pretransient oxide on LOCA high temperature steam oxidation and post-quench mechanical properties of Zircaloy-4 and M5 TM cladding, Water Reactor Fuel Performance Meeting, 2011. ,
Influence of hydrogen content on the ?/? phase transformation temperatures and on the thermal-mechanical behavior of Zy-4, M4 (ZrSnFeV), and M5 TM (ZrNbO) alloys during the first phase of LOCA transient, Thirteenth International Symposium, 2002. ,
The breakaway oxidation of zirconium and its alloys a review, J. Common Met, vol.39, issue.1, pp.99-107, 1975. ,
Comparative studies on high-temperature corrosion of ZrNb1 and Zircaloy-4', Nucl. Eng. Des, vol.147, issue.1, pp.53-62, 1994. ,
Pressure effects on high temperature steam oxidation of zircaloy-4, Met. Mater. Int, vol.7, issue.4, pp.367-373, 2001. ,
Oxidation kinetics of Zircaloy-4 and Zr-1Nb-1Sn-0.1Fe at temperatures of 700-1200°C', J. Nucl. Mater, vol.335, issue.3, pp.443-456, 2004. ,
High-temperature oxidation behavior of Zircaloy-4 and Zirlo in steam ambient, J. Mater. Sci. Technol, vol.26, issue.9, pp.827-832, 2010. ,
Transformations and cracks in zirconia films leading to breakaway oxidation of Zircaloy, Acta Mater, vol.61, issue.11, pp.3923-3935, 2013. ,
Microstructural characterization of ZrO2 layers formed during the transition to breakaway oxidation, J. Nucl. Mater, vol.399, issue.2, pp.208-211, 2010. ,
Etude micrographique du processus de desquamation ("break-away") au cours de l'oxydation du zirconium, J. Common Met, vol.14, issue.2, pp.181-200, 1968. ,
Crystal structure of orthorhombic zirconia in partially stabilized zirconia, J. Am. Ceram. Soc, vol.72, issue.9, pp.1757-1760, 1989. ,
A working hypothesis on oxidation kinetics of Zircaloy, J. Nucl. Mater, vol.299, issue.3, pp.235-241, 2001. ,
O-Zr (Oxygen-Zirconium), J. Phase Equilibria Diffus, vol.28, issue.5, pp.498-498, 2007. ,
Raman spectroscopy study of the tetragonal-to-monoclinic transition in zirconium oxide scales and determination of overall oxygen diffusion by nuclear microanalysis of O 18, Zirconium in the Nuclear Industry: Ninth International Symposium, 1991. ,
How the tetragonal zirconia is stabilized in the oxide scale that is formed on a zirconium alloy corroded at 400 °C in steam, Zirconium in the nuclear industry: Tenth international symposium, 1994. ,
The occurrence of metastable tetragonal zirconia as a crystallite size effect, J. Phys. Chem, vol.69, issue.4, pp.1238-1243, 1965. ,
Neutron diffraction study of the sizeinduced tetragonal to monoclinic phase transition in zirconia nanocrystals, Phys. Rev. Lett, vol.90, issue.21, p.216103, 2003. ,
Stress distribution measured by Raman spectroscopy in zirconia films formed by oxidation of Zr-based alloys, Zirconium in the Nuclear Industry: Twelfth International Symposium, 2000. ,
In-situ time-resolved study of structural evolutions in a zirconium alloy during high temperature oxidation and cooling, Mater. Charact, p.109971, 2019. ,
URL : https://hal.archives-ouvertes.fr/hal-02431028
LOCA Behavior of E110 Alloy, Nuclear Safety Research Conference, 2003. ,
Loss of Coolant Accident Testing Round Robin, 2013. ,
New insights in structural characterization of zirconium alloys oxidation at high temperature, J. Nucl. Mater, vol.429, issue.1, pp.19-24, 2012. ,
In-situ X-ray diffraction analysis of zirconia layer formed on zirconium alloys oxidized at high temperature, J. Nucl. Mater, vol.458, pp.245-252, 2015. ,
Oxidation kinetics and related phenomena of zircaloy-4 fuel cladding exposed to high temperature steam and hydrogen-steam mixtures under PWR accident conditions, Nucl. Eng. Des, vol.103, issue.1, p.90286, 1987. ,
The relationship between the amount of oxidation and activation energy on the steam oxidation reaction of Zircaloy-4 cladding, J. Nucl. Mater, vol.440, issue.1-3, pp.457-466, 2013. ,
Reaction behavior of zircaloy-4 in steam-hydrogen mixtures at high temperature, J. Nucl. Mater, vol.105, issue.2, pp.119-131, 1982. ,
Investigations of zircaloy-4 cladding oxidation under steam starvation and hydrogen blanketing conditions, 1984. ,
Oxidation kinetics of low-Sn Zircaloy-4 at the temperature range from 773 to 1,573 K', J. Nucl. Sci. Technol, vol.40, issue.4, pp.213-219, 2003. ,
Comparison of the High-Temperature Steam Oxidation Kinetics of Advanced Cladding Materials, Nucl. Technol, vol.170, issue.1, pp.272-279, 2010. ,
Raman investigation of pre-and post-breakaway oxide scales formed on Zircaloy-4 and M5® in air at high temperature, J. Nucl. Mater, vol.421, issue.1, pp.160-171, 2012. ,
URL : https://hal.archives-ouvertes.fr/hal-02907240
Monoclinic to tetragonal semireconstructive phase transition of zirconia, Phys. Rev. B, vol.67, issue.6, p.64111, 2003. ,
Phase Analysis in Zirconia Systems, J. Am. Ceram. Soc, vol.55, pp.303-305, 2006. ,
Modelling of the mechanical behavior of the metaloxide system during Zr alloy oxidation, J. Nucl. Mater, vol.256, issue.1, pp.35-46, 1998. ,
The oxidation behavior of Zircaloy-4 in steam between 600 and 1600° C', Mater. Corros, vol.36, issue.3, pp.105-116, 1985. ,
Oxidation of zirconium alloys in oxygen at high temperatures up to 1600 C, Oxid. Met, vol.70, issue.5-6, pp.317-329, 2008. ,
Experimental tests to validate the rate-limiting step assumption used in the kinetic analysis of solid-state reactions, Thermochim. Acta, vol.478, issue.1-2, pp.34-40, 2008. ,
URL : https://hal.archives-ouvertes.fr/emse-00590304