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Interfacial Segregation in Fast Reactor Irradiated 12% Chromium Martensitic Steel
TS. Morgan
EA. Little
RG. Faulkner
JM. Titchmarsh
出版
ASTM International
, 1992
URL
http://books.google.com.hk/books?id=o491zgEACAAJ&hl=&source=gbs_api
註釋
Interfacial solute segregation has been studied in FV448-grade 12% chromium martensitic stainless steel following fast reactor irradiation to damage levels of 25 and 46 dpa at temperatures of 400 and 465°C, respectively. The technique of field emission gun scanning transmission electron microscopy has been used to measure solute redistribution profiles, with high spatial resolution, across martensite lath boundaries. Significant nickel and silicon enrichments are detected at the lath boundaries. Chromium levels exhibit more complex behavior, with localized enrichment at the boundary itself but depletion in adjacent matrix regions. These radiation-induced segregation eifects imply that martensite lath boundaries act as major point-defect sinks during neutron irradiation. The magnitude of the silicon segregation is greatest at 400°C, whereas nickel and chromiun concentrations are relatively temperature insensitive. The data are broadly consistent with the current understanding of nonequilibrium segregation processes based on solute atom size effects.
