The discrepancies in multistep damage evolution of yttria-stabilized zirconia irradiated with different ions

Yang, Tonghai; Taylor, Christina; Kong, Shuyan; Wang, Chenxu; Zhang, Yongfeng; Huang, Xuejun; Xue, Jianming; Wang, Yugang

doi:10.1016/j.jnucmat.2013.06.033

Cited by 21 publications

(9 citation statements)

References 54 publications

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“…9(b) look different from those previously reported by the authors 18,27 or by another group also working on irradiated YSZ. 19 In particular, as previously explained in Ref. 29 and mentioned in Sec.…”

Section: Discussionmentioning

confidence: 58%

“…No amorphization has been detected, except when a significant concentration of particular atomic species such as Cs is introduced in the crystalline lattice, 16,17 but the required Cs concentration ($8%) is well above that expected in an IMF. When YSZ is irradiated in the nuclear energy-loss regime, it exhibits a multi-step damage build-up, 5,18,19 each step being characterized by a predominant type of radiation defects. For instance, in the first step, small defect clusters are preferentially formed; these clusters turn into dislocation loops in the second step and eventually a network of tangled dislocations is observed at the end of this step.…”

Section: Introductionmentioning

confidence: 99%

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Comprehensive study of the effect of the irradiation temperature on the behavior of cubic zirconia

Debelle

Channagiri

Thomé

et al. 2014

Journal of Applied Physics

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High-temperature stability of ion-implanted zirconia and spinel J. Appl. Phys. 97, 113509 (2005) ) and at five temperatures: 80, 300, 573, 773, and 1073 K. Irradiated samples have been characterized by Rutherford backscattering spectroscopy in channeling mode, X-ray diffraction and transmission electron microscopy techniques in order to determine the disordering kinetics. All experimental results show that, whatever is the irradiation temperature, the damage build-up follows a multi-step process. In addition, the disorder level at high fluence is very similar for all temperatures. Thus, no enhanced dynamic annealing process is observed. On the other hand, transitions in the damage accumulation process occur earlier in fluence with increasing temperature. It is shown that temperature as low as 573 K is sufficient to accelerate the disordering process in ion-irradiated YSZ. V C 2014 AIP Publishing LLC. [http://dx

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Section: Discussionmentioning

confidence: 58%

Section: Introductionmentioning

confidence: 99%

Comprehensive study of the effect of the irradiation temperature on the behavior of cubic zirconia

Debelle

Channagiri

Thomé

et al. 2014

Journal of Applied Physics

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“…Polycrystalline UO 2 irradiated with He ions exhibits a similar defect structure at a lower dose, 0.007–0.038, which is same with the case of ZrO 2 . However, it should be noted that although UO 2 shows a similar irradiation response with ZrO 2 , the quantitative comparison of irradiation tolerances of both fluorite‐type oxides should be careful due to the different irradiation conditions …”

Section: Discussionmentioning

confidence: 99%

Effects of He Irradiation on Yttria‐Stabilized Zirconia Ceramics

et al. 2014

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Effects of He irradiation on polycrystalline yttria-stabilized zirconia (YSZ) are studied with the focus on irradiation-induced damage buildup, He behavior, and volume swelling. The evolution of irradiation-induced structural damage in polycrystalline YSZ, which is independent of grain orientation, is described by a multistep damage accumulation model. A three-step damage evolution process was found, and different types of defects were observed in the different damage steps. Compared with singlecrystal YSZ, the second damage step occurs at a lower dose in polycrystalline YSZ due to the initial defects and strain. The implanted He ions are readily trapped along the grain boundaries and the mobility of He ions is greatly increased. The enhanced He mobility along the grain boundary leads to a lower threshold irradiation dose and a larger penetration depth for bubble formation. Similar morphologies are observed for the He bubbles in the polycrystalline YSZ and in single-crystal YSZ, and the formation of He bubbles in polycrystalline YSZ is not influenced by grain orientation. As both the extended defects and He bubbles can induce volume swelling, the variation in volume swelling as a function of dose can be divided into a two stage process.

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“…Since the early 1980's, research works dealing with the study, by XRD, of the strain induced by ion (or even neutron and electron) energy deposition have covered a wide range of materials, including mainly semiconductors 24,[28][29][30][31][32] and insulators 16,[33][34][35][36] but also, though more recently, metals 15,[37][38][39] . In all these works, two steps in the development of strain are observed.…”

Section: Current State Of Knowledge and Issues Addressed In This Workmentioning

confidence: 99%

Lattice strain in irradiated materials unveils a prevalent defect evolution mechanism

Debelle

Crocombette

Boulle

et al. 2018

Phys. Rev. Materials

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Modification of materials using ion beams has become a widespread route to improve or design materials for advanced applications, from ion doping for microelectronic devices to emulation of nuclear reactor environments. Yet, despite decades of studies, major issues regarding ion/solid interactions are not solved, one of them being the lattice-strain development process in irradiated crystals. In this work, we address this question using a consistent approach that combines X-ray diffraction (XRD) measurements with both molecular dynamics (MD) and rate equation cluster dynamics (RECD) simulations. We investigate four distinct materials that differ notably in terms of crystalline structure and nature of the atomic bonding. We demonstrate that these materials exhibit a common behaviour with respect to the strain development process. In fact, a strain build-up followed by a strain relaxation is observed in the four investigated cases. The strain variation is unambiguously ascribed to a change in the defect configuration, as revealed by MD simulations. Strain development is due to the clustering of interstitial defects into dislocation loops, while the strain release is associated with the disappearance of these loops through their integration into a network of dislocation lines. RECD calculations of strain depth profiles, which are in agreement with experimental data, indicate that the driving force for the change in the defect nature is the defect clustering process. This study paves the way for quantitative predictions of the microstructure changes in irradiated materials.

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The discrepancies in multistep damage evolution of yttria-stabilized zirconia irradiated with different ions

Cited by 21 publications

References 54 publications

Comprehensive study of the effect of the irradiation temperature on the behavior of cubic zirconia

Comprehensive study of the effect of the irradiation temperature on the behavior of cubic zirconia

Effects of He Irradiation on Yttria‐Stabilized Zirconia Ceramics

Lattice strain in irradiated materials unveils a prevalent defect evolution mechanism

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