Journal
JOURNAL OF NUCLEAR MATERIALS
Volume 329, Issue -, Pages 1388-1392Publisher
ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2004.04.203
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Oxide dispersion strengthened (ODS) steels are being developing for application as advanced fast reactor cladding and fusion blanket materials, in order to allow increased operation temperature. Oxidation testing of ODS steel was conducted under a controlled dry air atmosphere to evaluate the high temperature oxidation behavior. This showed that 9Cr-ODS martensitic steels and 12Cr-ODS ferritic steels have superior high temperature oxidation resistance compared to 11 mass% Cr PNC-FMS and 17 mass% Cr ferritic stainless steel. This high temperature resistance is attributed to earlier formation of the protective alpha-Cr2O3 on the outer surface of ODS steels. (C) 2004 Elsevier B.V. All rights reserved.
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