Diffusion in the bulk and in a symmetric tilt grain boundary of the Fe Cr system
Author:
Funder
CONICET
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference36 articles.
1. The mechanism of radiation-induced segregation in ferritic–martensitic alloys
2. Application of the inverse Kirkendall model of radiation-induced segregation to ferritic–martensitic alloys
3. Ab-initio based modeling of diffusion in dilute bcc Fe–Ni and Fe–Cr alloys and implications for radiation induced segregation
4. Dependence on grain boundary structure of radiation induced segregation in a 9wt.% Cr model ferritic/martensitic steel
5. Diffusion behavior of Cr diluted in bcc and fcc Fe: Classical and quantum simulation methods
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1. Corrosion behavior of Ni–25Cr–10Fe–3Si–xMo alloys beneath KCl–ZnCl2 deposits at 650°C: Role of long‐term aging;Materials and Corrosion;2024-03-25
2. Molecular dynamics study of the interaction between symmetric tilt Σ5(2 1 0) 〈0 0 1〉 grain boundary and radiation-induced point defects in Fe-9Cr alloy;Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms;2019-07
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