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Grain Boundary Modification During Neutron Irradiation at Intermediate Temperatures

Published online by Cambridge University Press:  21 March 2011

S. M. Bruemmer,
D. J. Edwards,
V. Y. Gertsman and
E. P. Simonen
S. M. Bruemmer
Affiliation:
Pacific Northwest National Laboratory P.O. Box 999, Richland, WA 99532
D. J. Edwards
Affiliation:
Pacific Northwest National Laboratory P.O. Box 999, Richland, WA 99532
V. Y. Gertsman
Affiliation:
Pacific Northwest National Laboratory P.O. Box 999, Richland, WA 99532
E. P. Simonen
Affiliation:
Pacific Northwest National Laboratory P.O. Box 999, Richland, WA 99532
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Abstract

Grain boundary compositions and near-boundary microstructures have been measured in complex Fe-Cr-Ni alloys after neutron irradiation at intermediate temperatures where nanometer-scale damage promotes structural integrity problems in nuclear reactor systems. Radiation-induced segregation (RIS) and dislocation loop microstructures have been determined as a function of irradiation dose up to 13 dpa and at temperatures near 280°C. The most significant effect on RIS was the grain boundary structure (low-energy special boundaries versus high-energy random boundaries) and composition (enrichment of Cr and Mo) before irradiation. Grain boundary character distribution did not change with irradiation and only high-energy boundaries exhibited significant radiation-induced changes. The initial grain boundary composition in mill-annealed stainless steels was difficult to remove during subsequent irradiation and retarded the development of Cr- and Mo-depleted regions.

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References

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