Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation

被引：120

作者：

Allen, T. R. ^{[1
]}

Gan, J. ^{[2
]}

Cole, J. I. ^{[2
]}

Miller, M. K. ^{[3
]}

Busby, J. T. ^{[3
]}

Shutthanandan, S. ^{[4
]}

Thevuthasan, S. ^{[4
]}

机构：

[1] Univ Wisconsin, Madison, WI 53706 USA

[2] Idaho Natl Lab, Idaho Falls, ID USA

[3] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA

[4] Pacific NW Natl Lab, Richland, WA 99352 USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 2008年 / 375卷 / 01期

关键词：

D O I：

10.1016/j.jnucmat.2007.11.001

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Ferritic-martensitic (FM) alloys are expected to play an important role as cladding or structural components in Generation IV systems operating in the temperature range 350-700 degrees C and to doses up to 200 dpa. Oxide dispersion strengthened (ODS) ferritic-martensitic steels have been developed to operate at higher temperatures than traditional FM steels. These steels contain nanometer-sized Y-Ti-O nanoclusters as a strengthening mechanism. Heavy ion irradiation has been used to determine the nanocluster stability over a temperature range of 500-700 degrees C to doses of 150 dpa. At all temperatures, the average nanocluster size decreases but the nanocluster density increases. The increased density of smaller nanoclusters under radiation should lead to strengthening of the matrix. While a reduction in size under irradiation has been reported in some other studies, many report oxide stability. The data from this study are contrasted to the available literature to highlight the differences in the reported radiation response. (C) 2007 Elsevier B.V. All rights reserved.

引用

页码：26 / 37

页数：12

共 39 条

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