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Production rates in long-term predictive radiation damage accumulation modelsare generally considered independent of the material's microstructure forreactor components. In this study, the effect of pre-existing microstructuralelements on primary damage production in alpha-Zr -- and vice-versa -- isassessed by molecular dynamics (MD) simulations. a-type dislocation loops,c-component dislocation loops and a tilt grain boundary (GB) were considered.Primary damage production is reduced in the presence of all thesemicrostructural elements, and clustering behavior is dependent on themicrostructure. Collision cascades do not cause a-type loop growth orshrinkage, but they cause c-component loop shrinkage. Cascades in the presenceof the GBs produce more vacancies than interstitials. This result, as well asother theoretical, MD and experimental evidence, confirm that vacancy loopswill grow in the vacancy supersaturated environment near GBs. Distincttemperature-dependent growth regimes are identified. Also, MD revealscascade-induced events where a-type vacancy loops are absorbed by GBs. Fesegregation at the loops inhibits this cascade-induced absorption.

Primary damage production in the presence of extended defects and growth of vacancy-type dislocation loops in hcp zirconium