T. Fuketa, H. Sasajima, Y. Mori, and K. Ishijima, Fuel failure and fission gas release in high burnup PWR fuels under RIA conditions, J. Nucl. Mater, vol.248, p.249, 1997.

T. Fuketa and T. Sugiyama, Nuclear fuel behavior during RIA, OCDE/NEA Workshop, 2009.

J. Papin, Eurosafe Meeting, 2003.

J. Papin, B. Cazalis, and J. M. Frizonnet, Summary and interpretation of the CABRI REP-Na program, Nucl. Technol, vol.157, p.230, 2007.

V. Georgenthum, WRFPM Conference, 2008.

J. Desquines, Proceedings of the ASTM conference on Zirconium in the Nuclear Industry, 2004.

B. Michel, C. Nonon, J. Sercombe, F. Michel, and V. Marelle, Simulation of pellet-cladding interaction with the pleiades fuel performance software environment, Nucl. Technol, vol.182, p.124, 2013.

, CAST3M

J. Sercombe, I. Aubrun, and C. Nonon, Power ramped cladding stresses and strains in 3D simulations with burnup-dependent pellet-clad friction, Nucl. Eng. Des, vol.242, p.164, 2012.

J. Sercombe, TopFuel Conference, 2010.

M. L. Saux, J. Besson, S. Carassou, C. Poussard, and X. Averty, A model to describe the anisotropic viscoplastic mechanical behavior of fresh and irradiated Zircaloy-4 fuel claddings under RIA loading conditions, J. Nucl. Mater, vol.378, p.60, 2008.
URL : https://hal.archives-ouvertes.fr/hal-00311854

B. Cazalis, J. Desquines, and C. Poussard, The PROME-TRA program: Fuel cladding mechanical behavior under high strain rate, Nucl. Technol, vol.157, p.215, 2007.

A. H. De-ménibus, Q. Auzoux, and O. Dieye, Formation and characterization of hydride blisters in Zircaloy-4 cladding tubes, J. Nucl. Mater, vol.449, p.132, 2014.

V. Macdonald, D. L. Boulch, A. H. De-ménibus, J. Besson, Q. Auzoux et al., Fracture of Zircaloy-4 fuel cladding tubes with hydride blisters, Procedia Mater. Sci, vol.3, p.233, 2014.
URL : https://hal.archives-ouvertes.fr/hal-01053640

A. Hermann, Proceedings of the 15th ASTM conference on Zirconium in the Nuclear Industry, 2007.

M. L. Saux, J. Besson, and S. Carassou, A model to describe the mechanical behavior and the ductile failure of hydrided Zircaloy-4 fuel claddings between 25°C and 480°C, J. Nucl. Mater, vol.466, p.43, 2015.
URL : https://hal.archives-ouvertes.fr/hal-01199626

H. M. Chung and T. F. Kassner, Cladding metallurgy and fracture behavior during reactivity-initiated accidents at high burnup, Nucl. Eng. Des, vol.186, p.411, 1998.

Y. Udagawa, T. Mihara, T. Sugiyama, M. Suzuki, and M. Amaya, Simulation of the fracture behavior of Zircaloy-4 cladding under reactivity-initiated accident conditions with a damage mechanics model combined with fuel performance codes FEMAXI-7 and RANNS, J. Nucl. Sci. Technol, vol.51, p.208, 2014.