J. C. Brachet, Study of secondary hydriding at high temperature in zirconium based nuclear fuel cladding tubes by coupling information from neutron radiography/tomography, electron probe micro analysis, micro elastic recoil detection analysis and laser induced breakdown spectroscopy microprobe, Journal of Nuclear Materials, vol.448, pp.267-286, 2017.
URL : https://hal.archives-ouvertes.fr/cea-01488896

A. Pshenichnikov, Microstructure and mechanical properties of Zircaloy-4 cladding hydrogenated at temperatures typical for loss-of-coolant accident (LOCA) conditions, Nuclear Engineering and Design, vol.283, pp.33-39, 2015.

I. Turque, Mechanical behavior at high temperature of highly oxygen-or hydrogen-enriched ? and (prior-) ? phases of zirconium alloys, Zirconium in the Nuclear Industry: 18th International Symposium, ASTM STP 1597, pp.240-280, 2017.

N. Dupin, A Thermo-dynamic Database for Zirconium Alloys, Journal of Nuclear Materials, vol.275, pp.287-295, 1999.