Analysis of atomic distribution in as-fabricated Zircaloy-2 claddings by atom probe tomography under high-energy pulsed laser

Sawabe, Takashi; Sonoda, Tatsuhiko; Kitajima, S.; Kameyama, Tetsuya

doi:10.1016/j.jnucmat.2013.08.048

Cited by 20 publications

(3 citation statements)

References 14 publications

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“…The dislocation density was too low to detect the difference between these three alloys by TEM; the difference of dislocation density is regarded as negligibly small. Regarding solute concentration preceding APT studies revealed that the concentration of solute Sn dissolved in the Zr matrix of zircaloy-2 is in good agreement with its solubility at 853 K [26], indicating that precipitation does not occur below this temperature due to low diffusivity. Since the diffusivity of Nb and Sn in hcp Zr is similar [27e29], the equilibrium Nb concentration at 853 K is expected to be largely retained in the matrix.…”

Section: Obstacle Strength Of Bcc Nb Particlesmentioning

confidence: 89%

The effect of crystallographic mismatch on the obstacle strength of second phase precipitate particles in dispersion strengthening: bcc Nb particles and nanometric Nb clusters embedded in hcp Zr

et al. 2016

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Section: Obstacle Strength Of Bcc Nb Particlesmentioning

confidence: 89%

The effect of crystallographic mismatch on the obstacle strength of second phase precipitate particles in dispersion strengthening: bcc Nb particles and nanometric Nb clusters embedded in hcp Zr

et al. 2016

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“…These maps were quantified in at.% and the atomic fraction Fe/Cr map in c) was calculated. [9], [35] for α-annealed and β-treated material as squares and triangles, respectively, [10], [42], [49] and [12] , and analysis by atom probe tomography by [69]. Although quantification maps in the neutron-irradiated material demonstrated a lot of noise due to low concentrations in the transmission direction, obtaining the average concentration of all pixels with an alloying element concentration above background (> ~1 at.%) at high magnification after long counting times (> 30 minutes at 20 kcps) gave reliable Fe/X (X = Cr, Ni) ratios.…”

Section: Spp Dissolutionmentioning

confidence: 99%

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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“…Development in instrumentation in recent years has brought a surge of interest in APT for Zr alloy applications, prompting several publications on basic metallurgy and autoclave corrosion properties [9][10][11][12][13][14]. The aim of this study is to elucidate how irradiation affects the distribution of alloying elements in Zircaloy-2.…”

Section: Introductionmentioning

confidence: 99%

Redistribution of alloying elements in Zircaloy-2 after in-reactor exposure

Sundell

Thuvander

Tejland

et al. 2014

Journal of Nuclear Materials

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h i g h l i g h t sWe have conducted an atom probe tomography study on a Zircaloy-2 fuel cladding material that has been subjected to 9 annual cycles of in-reactor exposure.The results show that large numbers of nanosized Fe and Cr rich particles have precipitated along parallel planes in the matrix. Fe and Sn are seen to segregate to ring-shaped features that are interpreted to be c-loops. A sub-oxide of approximate composition ZrO is found at the metal-oxide interface. a b s t r a c tAn atom probe tomography study of the microstructure of a Zircaloy-2 material subjected to 9 annual cycles of BWR exposure has been conducted. Upon dissolution of secondary phase particles, Fe and Cr are seen to reprecipitate in large numbers of clusters and particles of 1-5 nm sizes throughout the Zr metal matrix. Fe and Sn were observed to segregate to ring-shaped features in the metal that are interpreted to be -component vacancy loops. This implies that these two elements play a major role in the irradiation growth phenomenon in Zr alloys, which is believed to be caused by the formation of -loops. Similarly to autoclave-corroded Zr alloys, the formation of a sub-oxide layer of approximate composition ZrO was observed. On the other hand, no oxygen saturated metal phase was detected underneath the oxide scale.

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Analysis of atomic distribution in as-fabricated Zircaloy-2 claddings by atom probe tomography under high-energy pulsed laser

Cited by 20 publications

References 14 publications

The effect of crystallographic mismatch on the obstacle strength of second phase precipitate particles in dispersion strengthening: bcc Nb particles and nanometric Nb clusters embedded in hcp Zr

The effect of crystallographic mismatch on the obstacle strength of second phase precipitate particles in dispersion strengthening: bcc Nb particles and nanometric Nb clusters embedded in hcp Zr

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

Redistribution of alloying elements in Zircaloy-2 after in-reactor exposure

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