Abstract
Annealed Zircaloy-2 was neutron irradiated to 20 dpa at 690 K. Irradiation-induced dislocation structures in the matrix consisted of dense loop and network dislocations, having Burgers vectors, b = 1 3 〈1120〉 , as well as a high density of c- component dislocations. Intermetallic precipitates underwent irradiation-induced dissolution resulting in higher solute concentration within the grains. There were solute concentration gradients and irradiation-enhanced precipitates at the grain boundaries and these were non-uniformally distributed. In-situ post-irradiation annealing in an HVEM enabled continuous observation of the evolving dislocation structure. Dislocations were found to have Burgers vectors of the pure c- type , 〈a + c〉-type and pure a- type . The formation of the c- component dislocations and their relevance to irradiation-induced growth are discussed. Based on these observations, recommendations are made as to possibly alterations to the chemistry of Zircaloy-2 that might reduce the magnitude of irradiation growth.
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