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Kaito, T.; Narita, T.; Ukai, S.; Matsuda, Y., E-mail: takeji@oec.jnc.go.jp2004
AbstractAbstract
[en] 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 α-Cr2O3 on the outer surface of ODS steels
Primary Subject
Source
ICFRM-11: 11. International conference on fusion reactor materials; Kyoto (Japan); 7-12 Dec 2003; S0022311504003538; Copyright (c) 2004 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Literature Type
Conference
Journal
Country of publication
ALLOYS, CARBON ADDITIONS, CHALCOGENIDES, CHEMICAL REACTIONS, CHROMIUM COMPOUNDS, DEPOSITION, EPITHERMAL REACTORS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, OXIDES, OXYGEN COMPOUNDS, REACTOR COMPONENTS, REACTORS, STEELS, SURFACE COATING, TRANSITION ELEMENT ALLOYS, TRANSITION ELEMENT COMPOUNDS
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