کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
1565064 | 1514188 | 2015 | 10 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Epitaxial Fe/Y2O3 interfaces as a model system for oxide-dispersion-strengthened ferritic alloys
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موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
انرژی هسته ای و مهندسی
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چکیده انگلیسی
The fundamental mechanisms underlying the superior radiation tolerance properties of oxide-dispersion-strengthened ferritic steels and nanostructured ferritic alloys are poorly understood. Thin film heterostructures of Fe/Y2O3 can serve as a model system for fundamental studies of radiation damage. Epitaxial thin films of Y2O3 were deposited by pulsed laser deposition on 8% Y:ZrO2 (YSZ) substrates with (1Â 0Â 0), (1Â 1Â 0), and (1Â 1Â 1) orientation. Metallic Fe was subsequently deposited by molecular beam epitaxy. Characterization by X-ray diffraction and Rutherford backscattering spectrometry in the channeling geometry revealed a degree of epitaxial or axiotaxial orientation for Fe(2Â 1Â 1) deposited on Y2O3(1Â 1Â 0)/YSZ(1Â 1Â 0). In contrast, Fe on Y2O3(1Â 1Â 1)/YSZ(1Â 1Â 1) was fully polycrystalline, and Fe on Y2O3(1Â 0Â 0)/YSZ(1Â 0Â 0) exhibited out-of-plane texture in the [1Â 1Â 0] direction with little or no preferential in-plane orientation. Scanning transmission electron microscopy imaging of Fe(2Â 1Â 1)/Y2O3(1Â 1Â 0)/YSZ(1Â 10) revealed a strongly islanded morphology for the Fe film, with no epitaxial grains visible in the cross-sectional sample. Well-ordered Fe grains with no orientation to the underlying Y2O3 were observed. Well-ordered crystallites of Fe with both epitaxial and non-epitaxial orientations on Y2O3 are a promising model system for fundamental studies of radiation damage phenomena. This is illustrated with preliminary results of He bubble formation following implantation with a helium ion microscope. He bubble formation is shown to preferentially occur at the Fe/Y2O3 interface.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 457, February 2015, Pages 352-361
Journal: Journal of Nuclear Materials - Volume 457, February 2015, Pages 352-361
نویسندگان
T.C. Kaspar, M.E. Bowden, C.M. Wang, V. Shutthanandan, N.R. Overman, R.M. van Ginhoven, B.D. Wirth, R.J. Kurtz,