The effect of Cu on irradiation-induced growth mechanisms in Zr alloys following neutron irradiation

Irradiation-induced growth (IIG) limits fuel assembly lifespan, which is driven by <a> type dislocation loops with b = 1/3<11-20> and <c> type dislocation loops with b = 1/6<20-23>. Copper (Cu) is becoming more common as an alloying addition in zirconium (Zr). However, there is limited research on the behaviour of Cu in Zr alloys, particularly surrounding IIG effects following irradiation. The recrystalised Zr-Nb-Sn-Cu-Fe W13 alloy developed by Westinghouse Electric Company was proton irradiated at the Dalton Cumbria Facility and neutron irradiated in the BOR-60 research reactor. The purpose of this study was to understand the behaviour of Cu in the W13 alloy following irradiation, particularly how Cu influenced microstructural and dislocation loop evolution.