Title of article
Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation
Author/Authors
Allen، نويسنده , , T.R. and Gan، نويسنده , , J. and Cole، نويسنده , , J.I. and Miller، نويسنده , , M.K. and Busby، نويسنده , , J.T. and Shutthanandan، نويسنده , , S. and Thevuthasan، نويسنده , , S.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2008
Pages
12
From page
26
To page
37
Abstract
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 °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 °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.
Journal title
Journal of Nuclear Materials
Serial Year
2008
Journal title
Journal of Nuclear Materials
Record number
1367134
Link To Document