A polycrystalline modeling of the mechanical behavior of neutron irradiated zirconium alloys

• Published in: Journal of nuclear materials Vol. 384; no. 2; pp. 163 - 174
• Main Authors: Onimus, Fabien, Béchade, Jean-Luc
• Format: Journal Article
• Language: English
• Published: Amsterdam Elsevier B.V 15.02.2009; Elsevier
• Subjects: Applied sciences; Controled nuclear fusion plants; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Fuels; Installations for energy generation and conversion: thermal and electrical energy; Nuclear fuels; 62.20.fq; 61.82.Bg; Hardening; Tube; Mechanical properties; Zirconium alloy; Neutron irradiation; Clad; Microstructure; Modeling; Low cycle fatigue; Nuclear reactor
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2008.11.006

Zirconium alloys used as fuel cladding tubes in the nuclear industry undergo important changes after neutron irradiation in the microstructure as well as in the mechanical properties. However, the effects of the specific post-irradiation deformation mechanisms on the mechanical behavior are not clearly understood and modeled. Based on experimental results it is discussed that the kinematic strain hardening is increased by the plastic strain localization inside the dislocation channels as well as the only basal slip activation observed for specific mechanical tests. From this analysis, the first polycrystalline model is developed for irradiated zirconium alloys, taking into account the irradiation induced hardening, the intra-granular softening as well as the intra-granular kinematic strain hardening due to the plastic strain localization inside the channels. This physically based model reproduces the mechanical behavior in agreement with the slip systems observed. In addition, this model reproduces the Bauschinger effect observed during low cycle fatigue as well as the cyclic strain softening.