Irradiation-induced microstructural changes in Zr-1% Sn-1% Nb-0.4% Fe

Nikulina, A. V.; Markelov, V. A.; Peregud, M. M.; Voevodin, V. G.; Panchenko, V. L.; Kobylyansky, G. P.

doi:10.1016/s0022-3115(96)00453-9

Cited by 100 publications

(45 citation statements)

References 2 publications

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“…A metastable Zr 4 Fe phase has also been reported [14,21,29,31,32]. Unfortunately there is insufficient crystallographic information to conduct a reliable DFT study of Zr 4 Fe, therefore it was not considered further.…”

Section: Crystallography Of Intermetallic Phasesmentioning

confidence: 99%

Hydrogen solubility in zirconium intermetallic second phase particles

Burr

Murphy

Lumley

et al. 2013

Journal of Nuclear Materials

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The enthalpies of solution of H in Zr binary intermetallic compounds formed with Cu, Cr, Fe, Mo, Ni, Nb, Sn and V were calculated by means of density functional theory simulations and compared to that of H in α-Zr. It is predicted that all Zr-rich phases (formed with Cu, Fe, Ni and Sn), and those phases formed with Nb and V, offer lower energy, more stable sites for H than α-Zr. Conversely, Mo and Cr containing phases do not provide preferential solution sites for H. In all cases the most stable site for H are those that offer the highest coordination fraction of Zr atoms. Often these are four Zr tetrahedra but not always. Implications with respect to H-trapping properties of commonly observed ternary phases such as Zr(Cr,Fe) 2 , Zr 2 (Fe,Ni) and Zr(Nb,Fe) 2 are also discussed.

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Section: Crystallography Of Intermetallic Phasesmentioning

confidence: 99%

Hydrogen solubility in zirconium intermetallic second phase particles

Burr

Murphy

Lumley

et al. 2013

Journal of Nuclear Materials

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“…Efforts have also been made to identify the precipitates and the phase transitions causing the formation of these precipitates. [10,11,12] For example, Nikulina et al [13] have shown the presence of Zr 4 Sn and Zr 5 Sn 3 phases in the Zr-1Nb-1Sn-0.4Fe alloy.…”

Section: Introductionmentioning

confidence: 99%

Microstructural Evolution in Zr-1Nb and Zr-1Nb-1Sn-0.1Fe Alloys

Neogy

Srivastava

Chakravartty

et al. 2007

Metall Mater Trans A

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This article summarizes the evolution of microstructure in binary Zr-1Nb and quaternary Zr-1Nb-1Sn-0.1Fe alloys after (1) b quenching and tempering and (2) cold working and annealing. The morphologies of constituent phases and precipitates, their shape, size, and nature have been studied in detail using transmission electron microscopy (TEM). The b-quenched alloys, in general, exhibited a lath martensitic microstructure. On tempering, the martensitic microstructure underwent considerable changes with respect to the lath dimensions and precipitation behavior, ultimately leading to an equiaxed recrystallized microstructure. Annealing studies of cold-worked binary alloy showed precipitation of the b phase with varying Nb content depending on the heat-treatment temperature and time. In the quaternary alloy, precipitation of the Zr-Nb-Fe type phase along with the b phase took place on annealing the cold-worked samples. High-resolution electron microscopy (HREM) of the recrystallized microstructures was carried out to study the internal structure and the interface structure of the precipitating phases. In the annealing study, mechanical properties of the annealed samples were also determined. Microstructural observations together with mechanical property data concluded that in both alloys, complete recrystallization of the cold-worked microstructures took place on annealing the samples at 853 K for 1 hour.

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“…Still there is a search for new zirconium alloys for meeting the demands of high burn up fuels, higher coolant temperature and partial boiling of coolant. In this respect, binary Zr-Nb alloys containing about 0·5-2% Nb and quaternary Zr-Nb-Sn-Fe alloys have shown considerable promise (Sabol et al 1989(Sabol et al , 1991Nikulina et al 1996).…”

Section: Introductionmentioning

confidence: 99%

“…Several advanced zirconium based alloys, such as Zirlo (Zr-1Nb-1Sn-0·1Fe), Zr1Nb, Zr-0·1Nb-1·0Sn-0·2Fe-0·1Cr have been developed as candidate materials for fuel cladding tube which can support higher fuel burn up and a higher operating temperature. The irradiation induced point defects play a significant role on the microstructure, mechanical and creep properties of these alloys (Nikulina et al 1996). Several irradiation studies have been performed on zirconium based alloys over the past forty years.…”

Section: Introductionmentioning

confidence: 99%

Post irradiated microstructural characterization of Zr–1Nb alloy by X-ray diffraction technique and positron annihilation spectroscopy

et al. 2011

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Zr-1Nb samples were irradiated with 116 MeV O 5+ ions at different doses ranging from 5 × 10 17 to 8 × 10 18 O 5+ /m 2 . X-ray diffraction line profile analysis was performed to characterize the microstructural parameters of these samples. Average domain size, microstrain and dislocation density were estimated as a function of dose. An anomaly was observed in the values of these parameters at a dose of 2 × 10 18 O 5+ /m 2 . Positron annihilation spectroscopy was used to determine the existence and nature of vacancy clusters in the samples. Isochronal annealing was carried out for a sample to study the evolution of defect clusters.

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Irradiation-induced microstructural changes in Zr-1% Sn-1% Nb-0.4% Fe

Cited by 100 publications

References 2 publications

Hydrogen solubility in zirconium intermetallic second phase particles

Hydrogen solubility in zirconium intermetallic second phase particles

Microstructural Evolution in Zr-1Nb and Zr-1Nb-1Sn-0.1Fe Alloys

Post irradiated microstructural characterization of Zr–1Nb alloy by X-ray diffraction technique and positron annihilation spectroscopy

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