2016 Annual Meeting

Presentation information

Oral Presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 402-1. Nuclear Materials and the Irradiation Behavior

[1H14-21] ODS Structure materials Ni alloys

Sat. Mar 26, 2016 4:05 PM - 6:15 PM Room H (Lecture Rooms B B204)

Chair: Naoyuki Hashimoto (Hokkaido Univ.)

5:05 PM - 5:20 PM

[1H19] R&D of fuel cladding of ODS ferritic steel for maintaining fuel integrity at accidental high temperature condition (2)

(5)Order phase formation due to 8-15 wt.% Al addition in Fe-Cr-Al ferritic steels

*Bikas Maji1, Shigeharu Ukai1, Naoko Oono1, Takeji Kaito2, Tadahiko Torimaru3, Akihiko Kimura4, Shigenari Hayashi5 (1.Hokkaido University, 2.Japan Atomic Energy Agency, 3.Nippon Nuclear Fuel Development Co., LTD., 4.Kyoto University, 5.Tokyo Institute of Technology)

Keywords:ODS steels, Cladding tube material, Microstructural stability, Embrittlement

The embrittlement issue associated with the formation of Fe-Al intermetallic order phases has been investigated in Fe-Cr-Al ferritic steels. The Fe-(12-17)Cr-(8-15)Al-0.5Ti-0.5Y2O3 (wt.%) ODS ferritic steels were produced by mechanical alloying followed by spark plasma sintering and their microstructural stability and mechanical property have been evaluated after ageing at 475oC up to 1000 h.