Irradiation hardening and microstructure evolution of ion-irradiated Zr-hydride

Oono, Naoko; Kasada, Ryuta; Higuchi, Toru; Sakamoto, Kunio; Nakatsuka, Masafumi; Hasegawa, Akiko; Kondo, Sosuke; Matsui, Hideki; Kimura, Akihiko

doi:10.1016/j.jnucmat.2011.06.041

Cited by 13 publications

(5 citation statements)

References 18 publications

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“…This is exemplified in Figure 1, showing a detail of a diffractogram registered for a hydride blister, at a location where the volume fractions of -Zr and hydride were nearly equal. The -(220) and -(200) peaks are considerably wider than the - (11)(12)(13)(14)(15)(16)(17)(18)(19)(20) and -(10-11) peaks, respectively, even when the instrumental resolution is almost identical, due to the close proximity between the  and  peaks displayed in the figure. This motivated a thorough analysis of peak width, in order to extract some additional information from those past experiments.…”

Section: Samples and Testingmentioning

confidence: 94%

“…So, information about the elastic constants and deformation modes has been obtained from tests performed on bulk, homogeneous, crack-free hydrides produced from pure Zr in a modified Sieverts apparatus [14,15,16,17] and, more recently, also from Zr2.5%Nb [18].…”

Section: Introductionmentioning

confidence: 99%

“…show that plastic deformation of -hydride involves both slip and twinning. Slip on the {111}<110> system is the dominant deformation mechanism for as-produced single-phase bulk -hydride between room temperature and 250°C [15,19]. Dislocation lines and twin bands on a {110} twin plane are readily observed in TEM images as intrinsic defects in the as-produced bulk material [19].…”

Section: Introductionmentioning

confidence: 99%

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Quantification of dislocations densities in zirconium hydride by X-ray line profile analysis

et al. 2016

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Zirconium-based components in nuclear power plants are embrittled by precipitates of  zirconium hydride, which involves a martensitic-type transformation of the hexagonal -Zr lattice into the face-centered cubic Zr sublattice of the hydride. As a result, the hydride precipitates have a complex and heavily distorted internal structure that manifests as broad peaks in X-ray diffraction experiments. By a detailed analysis of the peak widths measured for different crystal planes we have found that most of this broadening is the result of dislocations. The analysis also showed that -hydride has very anisotropic mechanical elastic properties, in agreement with ab-initio simulations presented in the literature. Provided with this peak-broadening model, we have quantified dislocation densities within -hydrides precipitated in several Zr alloys, by analyzing previously published X-ray diffraction experiments performed at three synchrotron X-ray sources. The specimens investigated correspond to components affected by different hydride embrittling processes, namely: (i) samples from various components, charged in the laboratory with H contents in the 250 wt ppm range, (ii) laboratory-produced hydride blisters in Zr2.5%Nb pressure

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Section: Samples and Testingmentioning

confidence: 94%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Quantification of dislocations densities in zirconium hydride by X-ray line profile analysis

et al. 2016

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“…These materials are used for both academic and industrial research purpose [6]. Many reports are indeed for irradiation on metallic materials [6] with the series of effects such as irradiation hardening, microstructure effects and residual stresses development [7][8][9][10][11][12][13][14]. Single crystal and poly-crystalline zirconium, and its ion irradiation effects in-terms of irradiation hardening, microtexture changes, misorientation increasing and residual stresses development are addressed and reported [11][12][13][14].Irradiation also creates crystal defects which are mainly point defects (interstitial defect) and it was quantified by a parameter known as displacements per atom (dpa) [6,15].…”

Section: Introductionmentioning

confidence: 99%

Microtexture Study: Effect of Different Irradiation Sources on Zirconium and its Alloys

Revelly

2018

AMM

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The comparative study of Ga+ion, Nb+ion, proton and electron (H+and e-) irradiation on single crystal and poly crystal Zirconium (Zr), characterised in terms of misorientation profile change, EBSD maps or microtexture, XRD residual stresses development and irradiation hardening effect. It was concluded that the rate of damage is varying with respect to irradiation source. In the present study both the Zr and its alloys were used to conclude this main objective.

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“…[11] Both the macroscopic mechanical and the corrosion resistance properties are critical factors determining their eligibility for use in nuclear reactors. [12][13][14] The macroscopic properties of materials are directly affected by their microstructures, including the void concentration, [15] dislocation loops, [10,16] and secondary phase particles (SPP). [17,18] Different kinds of SPPs have been observed in differently fabricated zircaloys.…”

Section: Introductionmentioning

confidence: 99%

Microstructure evolution of zircaloy-4 during Ne ion irradiation and annealing: Anin situTEM investigation

Shen¹,

Peng²,

Zhou³

et al. 2014

Chinese Phys. B

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The microstructural evolution of zircaloy-4 was studied, including the amorphization and recrystallization of Zr(Fe, Cr) 2 precipitates, and the density of dislocations under in situ Ne ion irradiation and post annealing. The results show that irradiation at a relatively high temperature and dose induces the formation of nanocrystals in pre-amorphized Zr(Fe, Cr) 2 precipitates. The recrystallized nanocrystals also have the structure of hcp-Zr(Fe, Cr) 2 . The formation of the nanocrystals is thought to be the consequence of competition between atomistic disordering and the recrystallization of precipitates under ion irradiation. The free energy of the nanocrystal is lower than that of the amorphous state, which is another reason for the recrystallization of the precipitates. With increased annealing temperature, the density of the nanocrystals is increased. The dislocation density sharply decreases with the increase in the annealing temperature, and its size increases.

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Irradiation hardening and microstructure evolution of ion-irradiated Zr-hydride

Cited by 13 publications

References 18 publications

Quantification of dislocations densities in zirconium hydride by X-ray line profile analysis

Quantification of dislocations densities in zirconium hydride by X-ray line profile analysis

Microtexture Study: Effect of Different Irradiation Sources on Zirconium and its Alloys

Microstructure evolution of zircaloy-4 during Ne ion irradiation and annealing: Anin situTEM investigation

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