Microstructural and microchemical studies of Zr-2.5Nb pressure tube alloy

Perovic, V.; Perovic, A.; Weatherly, G. C.; Brown, L. M.; Purdy, G.R.; Fleck, R.G.; Holt, R.A.

doi:10.1016/0022-3115(93)90087-f

Cited by 51 publications

(19 citation statements)

References 12 publications

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“…The semi-quantification of SPP chemistry was consistently obtained from low symmetry orientations to avoid electron-channelling phenomena, and data were analysed within the FEI ESPRIT software. While it has been previously shown that it is necessary to subtract a blank background due to emitting 95Nb radiation from neutron-irradiated Zr-2.5wt.%Nb [32] and ZIRLO TM [33], the Zircaloy-2 studied here was of low enough activity for this to be unnecessary. In order to observe crystallographic nano-clustering in the matrix, it was necessary to obtain spectral images from high symmetry orientations.…”

Section: 2mentioning

confidence: 93%

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: 2mentioning

confidence: 93%

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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“…The major impurity in Zr-2.5Nb is Fe which is a b-stabilizer in Zr, and is primarily concentrated in the b-phase. Fe is also found at the a-a grain boundaries [44].…”

Section: 3mentioning

confidence: 98%

“…has not yet been satisfactorily explained. During irradiation it is dispersed into the a-phase [44], but whether it remains in solution or exists as sub-microscopic precipitates is not known. As a solute, it may affect the vacancy diffusion characteristics [63], while as a precipitate, it might provide recombination sites for vacancies and interstitials.…”

Section: Effect Of Fe Concentrationmentioning

confidence: 98%

“…As a solute, it may affect the vacancy diffusion characteristics [63], while as a precipitate, it might provide recombination sites for vacancies and interstitials. Also, its presence at a-a grain boundaries [44] could influence their role as sinks. Finally, Fe changes the volume fractions of a and b during extrusion, and could thus have an indirect influence through the texture.…”

Section: Effect Of Fe Concentrationmentioning

confidence: 99%

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In-reactor deformation of cold-worked Zr–2.5Nb pressure tubes

Holt

2008

Journal of Nuclear Materials

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197

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“…Although the effect is poorly understood, it is clear that iron is highly segregated to grain boundaries and to interphase boundaries [7] both in irradiated and heat-treated alloys. It is therefore worthwhile trying to detect the fine structure of the segregated iron to deduce if possible something about its chemical state, in particular its 3d occupancy.…”

Section: Experiments On Fe In Grain Boundaries Of Zr -5 (Wt) %Nb Alloysmentioning

confidence: 99%

Recent Studies of Near-Edge Structure

Brown

Walsh

Dray

et al. 1995

Microsc. Microanal. Microstruct.

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Abstract. 2014 The extent to which near-edge structure depends upon long-range order is explored using polymeric systems, where one can vary the disposition of side-groups and the degree of crystallinity and compare the resulting spectra. Carbon K-edges for polystyrene in atactic and isotactic forms are compared; the former is amorphous and the latter crystalline. Differences between the spectra are very slight but observable, and are attributed to bond orientation effects and to interaction between closely-spaced hydrogens bonded to neighbouring benzene rings and to the backbone. The quality of the spectra collected at doses of less than 300 e-nm-2 from a few square microns compares favourably with previously published EXAFS data. Another example of near-edge structure is provided by segregated species. The case of iron segregated to boundaries in Zr-Nb alloys is of intense interest to the nuclear industry. An attempt has been made to interpret observed fine structure in terms of structure from reference intermetallic compounds. It seems that the fine structure displayed by the segregated iron is different from that displayed by pure metallic iron or by known compounds with Zr, but more akin to ZrNbFe.Microsc. Microanal. Microstruct. 6 (1995) Figure 1. A benzene ring is attached to every other carbon atom of the carbon backbone. Each carbon atom has two different bonds to which the benzene ring can be attached. In isotactic polystyrene the rings are all attached to the same side of the carbon backbone. This isomer can be produced in both amorphous and crystalline forms. In atactic polystyrene the benzene rings are distributed at random on both sides of the carbon chain, which precludes the possibility of crystallization. Polystyrene was chosen because, by comparison to many polymers, it is less sensitive to irradiation damage by an electron beam. Spectra were acquired from amorphous atactic polystyrene, amorphous isotactic polystyrene and crystalline isotactic polystyrene. The amorphous films were produced by dissolving the polystyrene in toluene and drawing out a film on a glass slide. The crystals were produced as described by Tanzawa [1] and deposited from solution directly onto commercially produced SiO films on Cu

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Microstructural and microchemical studies of Zr-2.5Nb pressure tube alloy

Cited by 51 publications

References 12 publications

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

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

In-reactor deformation of cold-worked Zr–2.5Nb pressure tubes

Recent Studies of Near-Edge Structure

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