The irradiation of Zr was studied by using a kinetic Monte Carlo model. The initial cascade damage produced by 25keV recoils at 600K, deduced from molecular dynamics simulations, was used in the calculations. The evolution of the microstructure under fission irradiation conditions was followed to up to 0.5dpa. In particular, the influence of self-interstitial cluster migration upon the total defect concentration and size was analyzed. The results were compared with the available experimental data.

Influence of Self-Interstitial Mobility on Damage Accumulation in Zirconium under Fission Irradiation Conditions. C.Arevalo, M.J.Caturla, J.M.Perlado: Journal of Nuclear Materials, 2007, 362[2-3], 293-9