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

T. R. Allen, J. Gan, J. I. Cole, M. K. Miller, J. T. Busby, S. Shutthanandan, S. Thevuthasan

Research output: Contribution to journalArticle

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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.

Original languageEnglish
Pages (from-to)26-37
Number of pages12
JournalJournal of Nuclear Materials
Volume375
Issue number1
DOIs
Publication statusPublished - 30 Mar 2008
Externally publishedYes

Fingerprint

Heavy Ions
chromium oxides
Nanoclusters
Steel
Ion bombardment
nanoclusters
ion irradiation
Heavy ions
Chromium
heavy ions
steels
Radiation
Oxides
radiation
Martensitic steel
Ferritic steel
dosage
Temperature
oxides
Dosimetry

ASJC Scopus subject areas

  • Electronic, Optical and Magnetic Materials

Cite this

Allen, T. R., Gan, J., Cole, J. I., Miller, M. K., Busby, J. T., Shutthanandan, S., & Thevuthasan, S. (2008). Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation. Journal of Nuclear Materials, 375(1), 26-37. https://doi.org/10.1016/j.jnucmat.2007.11.001

Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation. / Allen, T. R.; Gan, J.; Cole, J. I.; Miller, M. K.; Busby, J. T.; Shutthanandan, S.; Thevuthasan, S.

In: Journal of Nuclear Materials, Vol. 375, No. 1, 30.03.2008, p. 26-37.

Research output: Contribution to journalArticle

Allen, TR, Gan, J, Cole, JI, Miller, MK, Busby, JT, Shutthanandan, S & Thevuthasan, S 2008, 'Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation', Journal of Nuclear Materials, vol. 375, no. 1, pp. 26-37. https://doi.org/10.1016/j.jnucmat.2007.11.001
Allen, T. R. ; Gan, J. ; Cole, J. I. ; Miller, M. K. ; Busby, J. T. ; Shutthanandan, S. ; Thevuthasan, S. / Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation. In: Journal of Nuclear Materials. 2008 ; Vol. 375, No. 1. pp. 26-37.
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