Microstructural aspects of accelerated deformation of Zircaloy nuclear reactor components during service

Griffiths, M.; Holt, R.A.; Rogerson, A.

doi:10.1016/0022-3115(94)00687-3

Cited by 108 publications

(41 citation statements)

References 17 publications

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“…The segregation is coincident with dislocation positions, which has been shown for Fe and Cr segregation in the vicinity of Fe-Cr type SPPs at similar distances from the SPPs to those presented here [12,64]. Recent calculations have shown that Fe, Cr and Ni diffusion is anisotropic with a preference in the 0001 direction [65], the diffusion of Zr self interstitials (SIAs) is anisotropic with preferable diffusion in the basal plane and the diffusion of vacancies is only weakly anisotropic [14,66].…”

Section: Spp Dissolution and Amorphisationsupporting

confidence: 83%

Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy

Harte

Topping

Frankel

et al. 2017

Journal of Nuclear Materials

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A. Harte et al., Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy J. Nucl. Mater. Accepted Jan. 2017 Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy (Fe,Ni). This is accomplished through ultra-high spatial resolution scanning transmission electron microscopy and the use of energy-dispersive X-ray spectroscopic methods. Fe-depletion is observed from both SPP types after irradiation with both irradiative species, but is heterogeneous in the case of Zr(Fe,Cr) 2 , predominantly from the edge region, and homogeneously in the case of Zr 2 (Fe,Ni). Further, there is evidence of a delay in the dissolution of the Zr 2 (Fe,Ni) SPP with respect to the Zr(Fe,Cr) 2 . As such, SPP dissolution results in matrix supersaturation with solute under both irradiative species and proton irradiation is considered well suited to emulate the effects of neutron irradiation in this context. The mechanisms of solute redistribution processes from SPPs and the consequences for irradiation-induced growth phenomena are discussed.

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Section: Spp Dissolution and Amorphisationsupporting

confidence: 83%

Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy

Harte

Topping

Frankel

et al. 2017

Journal of Nuclear Materials

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“…These results verify also the anisotropy of the growth strain rate tensor that has been used for modeling the deformation of Zr-2.5Nb pressure tubes [10] i.e., a substantially larger negative strain-rate in the normal direction than would be expected if the individual a-Zr crystals exhibited isotropic expansion in the basal plane, accompanied by shrinkage along the c-axis. This could be attributed either to the role of the grain boundaries (the grain shape is highly anisotropic) or to variations in the single crystal strain rate tensors with crystal orientation.…”

Section: Discussionsupporting

confidence: 81%

Volume conservation during irradiation growth of Zr–2.5Nb

Holt

Causey

2004

Journal of Nuclear Materials

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“…They found that the hci type dislocation loop lies on the basal plane and its Burgers vector isb ¼ 1=2h0 0 0 1i orb ¼ 1=6h2 0 2 3i along the c-axis. Unlike the hai type dislocation, the hci-type loop was strictly found to be a vacancy-type loop (Griffiths et al, 1995) and was considered responsible for the occurrence of breakaway growth (Northwood et al, 1979;Jostsons et al, 1977b). Holt and Gilbert (1986) examined the hci type dislocation loop of annealed zircaloys under a high fluence with 8.6 Â 10 25 n/m 2 between 553 and 584 K. In these results, hci-loops were observed for annealed zircaloy-2 and zircaloy-4 at greater than 3.0 Â 10 25 n/m 2 , while hai-loops were only shown for specimens irradiated with fluence below 3.0 Â 10 25 n/m 2 .…”

Section: Dislocation Loopsmentioning

confidence: 87%