期刊
JOURNAL OF NUCLEAR MATERIALS
卷 453, 期 1-3, 页码 334-339出版社
ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2014.06.050
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资金
- University of Michigan College of Engineering
- Nuclear Energy University Programs at the University of Michigan and University of California-Santa Barbara Colleges of Engineering
- Advanced Test Reactor National Scientific User Facility U.S. Department of Energy, Office of Nuclear Energy under DOE Idaho Operations Office [DE-AC07-051D14517]
The microstructural and chemical changes in a Fe-6 at.%Cr binary model alloy neutron irradiated to 1.82 dpa at 290 degrees C were investigated using atom probe tomography. After irradiation, Si and Cr are found segregated to dislocation loops, which were analyzed in terms of number density, size, and habit plane. Grain boundary chemistry was quantitatively compared between the as-received and the neutron irradiated alloys. The results are discussed in the context of equilibrium segregation, radiation-enhanced diffusion, and/or radiation induced segregation. (C) 2014 Elsevier B.V. All rights reserved.
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