Atomic scale investigation of radiation-induced segregation in austenitic stainless steels

被引：89

作者：

Etienne, A. ^{[1
,2
,3
]}

Radiguet, B. ^{[1
,2
]}

Cunningham, N. J. ^{[3
]}

Odette, G. R. ^{[3
]}

Pareige, P. ^{[1
,2
]}

机构：

[1] Univ Rouen, Grp Phys Mat, F-76801 St Etienne, France

[2] INSA Rouen, CNRS, UMR 6634, F-76801 St Etienne, France

[3] Univ Calif Santa Barbara, Dept Mat, Santa Barbara, CA 93106 USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 2010年 / 406卷 / 02期

基金：

美国国家科学基金会;

关键词：

STRESS-CORROSION CRACKING; GRAIN-BOUNDARY MISORIENTATION; SOLUTE SEGREGATION; MICROSTRUCTURAL EVOLUTION; ALLOY COMPOSITION; IRRADIATION; QUANTIFICATION; TEMPERATURE; DEPENDENCE;

D O I：

10.1016/j.jnucmat.2010.08.043

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Radiation-induced precipitation and segregation in a cold-worked 316 austenitic stainless steel irradiated with 10 MeV Fe5+ ions were characterized by atom probe tomography Ni and Si enrichment and Cr depletion were observed in roughly spherical and torus-shaped clusters believed to be due to solute enrichment and depletion at dislocation loops Solute segregation was also observed at network dislocations These observations are consistent with the phenomenon of radiation-induced segregation Radiation-induced segregation at grain boundaries was also studied at the near atomic scale Comparison of these observations with results from the literature shows a difference in the magnitude of the peak concentration of segregated solutes (C) 2010 Elsevier B V All rights reserved

引用

页码：244 / 250

页数：7

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