Development of FeCrAl-ODS steels for ATF cladding

Conference · Fri Jul 01 04:00:00 EDT 2016

OSTI ID:22764063

Ukai, S.; Oono, N. ^[1]; Ohtsuka, S.; Kaito, T. ^[2]; Sakamoto, K.; Torimaru, T. ^[3]; Kimura, A. ^[4]; Hayashi, S. ^[5]

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1. Materials Science and Engineering, Hokkaido University, Sapporo, Hokkaido 060-8628 (Japan)
2. Japan Atomic Energy Agency, Oarai, Ibaraki-prefecture 311-1393 (Japan)
3. Nippon Nuclear Fuel development Co., LTD., Oarai, Ibaraki-prefecture 311-1313 (Japan)
4. Institute of Advanced Energy, Kyoto University, Uji, Kyoto 611-0011 (Japan)
5. Materials Engineering, Tokyo Institute of Technology, Ookayama, Tokyo 152-8552 (Japan)

As an enhanced accident tolerant fuel (ATF) for LWR at severe accident condition, FeCrAl-ODS ferritic steels have been developed, and their applicability is being studied under the Japanese MEXT program. Alloying design of FeCrAl-ODS ferritic steels has been conducted, focusing on effect of mutual interaction of Cr-Al on oxidation resistance and α'-embrittlement. Effects of co-addition of Zr and excessive oxygen have also been studied to improve high-temperature strength. The ring tensile test of the manufactured claddings showed that tensile strength increases by Zr-addition and Zr-added FeCrAl-ODS steels have the highest strength among the existed steels at entire temperature range from room temperature up to 1000 Celsius degrees. Although Zr-addition sometimes leads to growth of alumina scale by rapid inward diffusion of oxygen through zirconia inside alumina, oxidation rate of Zr-added FeCrAl-ODS steels was successfully reduced to the level of Zr-free specimen by controlling oxygen content to form Y{sub 2}Zr{sub 2}O{sub 7} inside ODS steel matrix. This finding makes possible to improve not only high-temperature strength but also steam oxidation resistance in the Zr-added FeCrAl-ODS steels. (authors)

• Research Organization: American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22764063
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
ACCIDENT-TOLERANT NUCLEAR FUELS
ALUMINIUM OXIDES
CLADDING
EMBRITTLEMENT
FERRITIC STEELS
OXIDATION
OXYGEN
SEVERE ACCIDENTS
STEAM
TEMPERATURE RANGE 0273-0400 K
TEMPERATURE RANGE 0400-1000 K
TENSILE PROPERTIES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM ADDITIONS
ZIRCONIUM OXIDES