Helium irradiation of Y O -Fe bilayer system

Mairov, A.; Frazer, D.; Hosemann, Peter; Sridharan, Kumar

doi:10.1016/j.scriptamat.2018.11.006

Cited by 13 publications

(4 citation statements)

References 38 publications

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“…[19] However, only very weak in-plane orientation was observed [19]. Different from Kasper et al [19], Mairov et al [20] reported a cube-on-cube orientation relationship and a [111]Fe [001]Y 2 O 3 and (−12−1)Fe (110)Y 2 O 3 orientation relationship for Fe deposited on Y 2 O 3 thin film, which the latter are the most commonly. For Fe film on Y 2 O 3 film, experiments [21] showed that there exists a 63.8 Å thick region at the interface that differs from Fe and Y 2 O 3 .…”

Section: Introductionmentioning

confidence: 92%

First-principles investigations of hydrogen trapping in Y₂O₃ and the Y₂O₃|bcc Fe interface

Huang¹,

Hu²,

Wirth³

2020

J. Phys.: Condens. Matter

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Based on first-principles calculations, the binding energy of hydrogen atom to Y 2 O 3 and Y 2 O 3 |bcc Fe interface (relative to bcc Fe side) with cube-on-cube orientation is at least 0.45 eV, if hydrogen substitutional is considered, or at least 0.26 eV if only hydrogen interstitial is considered. The calculated binding energies do not have a unique fixed value, because they are dependent on the interface structure, the Fermi level of Y 2 O 3 near the interface and the chemical potential of Y/O. Hydrogen substitutional is more stable than hydrogen interstitial near the interface for Fermi level around calculated Schottky barrier height (SBH) at equilibrium. The Y 2 O 3 particle interior can be an effective trapping site for hydrogen. Hydrogen interstitial, hydrogen substitutional and Y/O vacancy have a much lower energy near the interface than within the Y 2 O 3 particle, presumably due to image charge interaction related to their non-zero charge state. For neutral impurities or defects, the energy near interface and that far away from the interface are similar ( 0.1 eV difference) for a perfect coherent interface. The Y 2 O 3 |bcc Fe interface should provide effective trapping sites for hydrogen atoms in oxide dispersion strengthened (ODS) steels.

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Section: Introductionmentioning

confidence: 92%

First-principles investigations of hydrogen trapping in Y₂O₃ and the Y₂O₃|bcc Fe interface

Huang¹,

Hu²,

Wirth³

2020

J. Phys.: Condens. Matter

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“…Other materials of interest for nuclear reactor design that have been the subject of HIM irradiation studies include silicon carbide grains in a pyrolytic carbon matrix [79], α-LiAlO 2 pellets [80], tristructural-isotropic fuel particles [81], oxide dispersion-strengthened steels [82], tungsten [83][84][85], an Fe-Zr alloy [86], a Y 2 O 3 /Fe bilayer [87], and nanocluster films of magnetite and core-shell iron-magnetite nanoparticles [88]. In these studies, various implantation effects have been investigated, including the tendency for grain boundaries and interfaces to act as sinks for irradiation-induced defects and implanted ions [79,80,82,83,86,87], and at higher doses, the subsurface swelling that results in blistering and delamination [84] (Figure 3d), which for deployment of a material in a reactor needs to be avoided [80,[82][83][84][85].…”

Section: Helium Nanobubbles and Blistersmentioning

confidence: 99%

A review of defect engineering, ion implantation, and nanofabrication using the helium ion microscope

Allen¹

2021

Beilstein J. Nanotechnol.

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The helium ion microscope has emerged as a multifaceted instrument enabling a broad range of applications beyond imaging in which the finely focused helium ion beam is used for a variety of defect engineering, ion implantation, and nanofabrication tasks. Operation of the ion source with neon has extended the reach of this technology even further. This paper reviews the materials modification research that has been enabled by the helium ion microscope since its commercialization in 2007, ranging from fundamental studies of beam–sample effects, to the prototyping of new devices with features in the sub-10 nm domain.

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“…In this case, the accumulation of helium in the structure of structural materials occurs as a result of its low solubility, as well as a high rate of mobility and the possibility of agglomeration. The emergence of helium in the structure occurs as a result of the initiated nuclear reactions under the effect of neutrons, and in the case of surface layer contact with the coolant [4,5,6,7,8,9,10]. Moreover, in the case of nuclear reactions, helium occurs in the entire volume of the material—that somewhat reduces the probability of agglomeration in the surface layer, while in the case of contact with the coolant, the main accumulation occurs in the small surface layer 0.5–1.0 μm thick.…”

Section: Introductionmentioning

confidence: 99%

Study of Helium Swelling in Nitride Ceramics at Different Irradiation Temperatures

2019

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This paper presents the results of a systematic study of helium swelling and the subsequent process of degradation of the near-surface layer of aluminum-based nitride ceramics. The samples were irradiated with 40 keV He2+ ions at temperatures of 300 and 1000 K with a fluence of 1 × 1017–5 × 1017 ions/cm2. The choice of radiation doses and temperature conditions was due to the possibility of simulating reactor tests of structural materials. It has been established that an increase in the irradiation fluence leads to the formation of large agglomerates of clusters of helium bubbles, as well as an increase in the degree of roughness and waviness of the surface with the formation of crater-like inclusions. In the case of irradiation at high temperatures, there was a slight decrease in the average size of helium inclusions compared with irradiation at room temperature. However, the density of inclusions and surface roughness were much higher. It is established that irradiation at room temperatures leads to a sharp decrease in ceramics density, as well as deformation of the crystal structure due to an increase in the density of dislocations and macrostresses in the structure. The decrease in ceramics density due to the formation of helium inclusions led to an increase in porosity and a defective fraction in the structure of the surface layer of ceramics.

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Helium irradiation of Y O -Fe bilayer system

Cited by 13 publications

References 38 publications

First-principles investigations of hydrogen trapping in Y₂O₃ and the Y₂O₃|bcc Fe interface

First-principles investigations of hydrogen trapping in Y₂O₃ and the Y₂O₃|bcc Fe interface

A review of defect engineering, ion implantation, and nanofabrication using the helium ion microscope

Study of Helium Swelling in Nitride Ceramics at Different Irradiation Temperatures

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Helium irradiation of Y O -Fe bilayer system

Cited by 13 publications

References 38 publications

First-principles investigations of hydrogen trapping in Y2O3 and the Y2O3|bcc Fe interface

First-principles investigations of hydrogen trapping in Y2O3 and the Y2O3|bcc Fe interface

A review of defect engineering, ion implantation, and nanofabrication using the helium ion microscope

Study of Helium Swelling in Nitride Ceramics at Different Irradiation Temperatures

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First-principles investigations of hydrogen trapping in Y₂O₃ and the Y₂O₃|bcc Fe interface

First-principles investigations of hydrogen trapping in Y₂O₃ and the Y₂O₃|bcc Fe interface