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Influence of Initial Grain Boundary Composition on the Evolution of Radiation-Induced Segregation Profiles

Published online by Cambridge University Press:  15 February 2011

J.T. Busby ,
G.S. Was ,
S.M. Bruemmer ,
D. J. Edwards  and
E.A. Kenik
J.T. Busby
Affiliation:
Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, Ml, 48109-2104, [email protected]
G.S. Was
Affiliation:
Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, Ml, 48109-2104
S.M. Bruemmer
Affiliation:
Pacific Northwest National Laboratory, Richland, WA, 99352
D. J. Edwards
Affiliation:
Pacific Northwest National Laboratory, Richland, WA, 99352
E.A. Kenik
Affiliation:
Metals and Ceramics Division, Oak Ridge National Laboratory, Oak Ridge, TN, 37831
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Abstract

Radiation-induced segregation (RIS) has been identified as a potential contributor to irradiation-assisted stress corrosion cracking (IASCC) of austenitic stainless steels in reactor core components. The occurrence of grain boundary segregation prior to irradiation influences both the shape and magnitude of RIS profile development during subsequent irradiation. In an effort to better understand the impact of this pre-irradiation enrichment on RIS profile development, the evolution of grain boundary Cr segregation profiles with irradiation dose has been characterized. Commercial purity and high-purity austenitic stainless steels with different initial levels of grain boundary Cr have been irradiated with neutrons (at 275°C) or protons (at 360-400°C) to doses up to ∼5 dpa. Grain boundary composition profiles were measured before and after irradiation using scanning transmission electron microscopy with energy dispersive xray spectroscopy (STEM-EDS). The initial enrichment of Cr is shown to delay radiation-induced Cr depletion and produce a “W-shaped” profile at low irradiation doses. Further irradiation causes the central peak of the W to decrease, eventually resulting in the classical “V-shaped” depletion profile. Possible mechanisms for the pre-irradiation enrichment and its evolution into a “W-shaped” profile will be discussed.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 540: Symposium N / Microstructural Processes in Irradiated Materials , 1998 , 451
Copyright
Copyright © Materials Research Society 1999

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