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The Measurement of Light Element Segregation Using EDS and EELS

Published online by Cambridge University Press:  02 July 2020

J.T. Busby ,
E.A. Kenik  and
G.S. Was
J.T. Busby
Affiliation:
The University of Michigan, Dept. of Nuclear Engineering and Radiological Sciences Ann Arbor, MI48109.
E.A. Kenik
Affiliation:
Metals and Ceramics Division, Oak Ridge National Laboratory, Oak Ridge, TN37831
G.S. Was
Affiliation:
The University of Michigan, Dept. of Nuclear Engineering and Radiological Sciences Ann Arbor, MI48109.
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Extract

Radiation-induced segregation (RIS) is the spatial redistribution of elements at defect sinks such as grain boundaries and free surfaces during irradiation. This phenomenon has been studied in a wide variety of alloys and has been linked to irradiation-assisted stress corrosion cracking (IASCC) of nuclear reactor core components. However, several recent studies have shown that Cr and Mo can be enriched to significant levels at grain boundaries prior to irradiation as a result of heat treatment. Segregation of this type may delay the onset of radiation-induced Cr depletion at the grain boundary, thus reducing IASCC susceptibility. Unfortunately, existing models of segregation phenomena do not correctly describe the physical processes and therefore are grossly inaccurate in predicting pre-existing segregation and subsequent redistribution during irradiation. Disagreement between existing models and measurement has been linked to potential interactions between the major alloying elements and lighter impurity elements such as S, P, and B.

Type
Spatially-Resolved Characterization of Interfaces in Materials
Information
Microscopy and Microanalysis , Volume 4 , Issue S2: Proceedings: Microscopy & Microanalysis '98, Microscopy Society of America 56th Annual Meeting, Microbeam Analysis Society 32nd Annual Meeting, Atlanta, Georgia July 12-16, 1998 , July 1998 , pp. 772 - 773
Copyright
Copyright © Microscopy Society of America

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References

References:

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6. This research was supported by the U.S. Department of Energy under grant DE-FG02-93ER-12310, by the Associated Western Universities-Northwest under U.S. Department of Energy grant DE-FG02-89ER-7552. Work also supported by Pacific Northwest National Laboratory and the Office of Basic Energy Sciences, Division of Materials Sciences, U.S. Department of Energy. Research partially supported by the Division of Materials Sciences, U.S. Department of Energy under contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corp., through the SHaRE Program under contract DE-AC05-76OR000333 with Oak Ridge Associated Universities.Google Scholar