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Cr incorporated phase transformation in Y2O3 under ion irradiation.
Li, N; Yadav, S K; Xu, Y; Aguiar, J A; Baldwin, J K; Wang, Y Q; Luo, H M; Misra, A; Uberuaga, B P.
Afiliação
  • Li N; Materials Physics and Applications Division, MPA-CINT, Los Alamos National Laboratory, Los Alamos, New Mexico 87545, USA.
  • Yadav SK; Materials Science and Technology Division, MST-8, Los Alamos National Laboratory, Los Alamos, New Mexico 87545, USA.
  • Xu Y; Department of Chemical and Materials Engineering, New Mexico State University, Las Cruces, New Mexico 88003, USA.
  • Aguiar JA; Idaho National Laboratory, Idaho Falls, Idaho, 83415, USA.
  • Baldwin JK; Materials Physics and Applications Division, MPA-CINT, Los Alamos National Laboratory, Los Alamos, New Mexico 87545, USA.
  • Wang YQ; Materials Science and Technology Division, MST-8, Los Alamos National Laboratory, Los Alamos, New Mexico 87545, USA.
  • Luo HM; Department of Chemical and Materials Engineering, New Mexico State University, Las Cruces, New Mexico 88003, USA.
  • Misra A; Department of Materials Science and Engineering, University of Michigan, Ann Arbor, Michigan 48109, USA.
  • Uberuaga BP; Materials Science and Technology Division, MST-8, Los Alamos National Laboratory, Los Alamos, New Mexico 87545, USA.
Sci Rep ; 7: 40148, 2017 01 16.
Article em En | MEDLINE | ID: mdl-28091522
ABSTRACT
Under irradiation, chemical species can redistribute in ways not expected from equilibrium behavior. In oxide-dispersed ferritic alloys, the phenomenon of irradiation-induced Cr redistribution at the metal/oxide interfaces has drawn recent attention. Here, the thermal and irradiation stability of the FeCr/Y2O3 interface has been systematically studied. Trilayer thin films of 90 nm Fe - 20 at.% Cr (1st layer)/100 nm Y2O3 (2nd layer)/135 nm Fe - 20 at.% Cr (3rd layer) were deposited on MgO substrates at 500 °C. After irradiation, Cr diffuses towards and enriches the FeCr/Y2O3 interface. Further, correlated with Cr redistributed into the oxide, an amorphous layer is generated at the interface. In the Y2O3 layer, the original cubic phase is observed to transform to the monoclinic phase after irradiation. Meanwhile, nanosized voids, with relatively larger size at interfaces, are also observed in the oxide layer. First-principles calculations reveal that Cr substitution of Y interstitials in Y2O3 containing excess Y interstitials is favored and the irradiation-induced monoclinic phase enhances this process. Our findings provide new insights that may aid in the development of irradiation resistant oxide-dispersed ferritic alloys.

Texto completo: 1 Base de dados: MEDLINE Idioma: En Ano de publicação: 2017 Tipo de documento: Article

Texto completo: 1 Base de dados: MEDLINE Idioma: En Ano de publicação: 2017 Tipo de documento: Article