Hostname: page-component-586b7cd67f-l7hp2 Total loading time: 0 Render date: 2024-11-27T01:57:12.898Z Has data issue: false hasContentIssue false
  • English
  • Français

Characterization of oxide particles in ODS austenitic stainless steel after heavy ion irradiation up to high doses

Published online by Cambridge University Press:  21 March 2011

Hiroshi Oka ,
Yosuke Yamazaki ,
Hiroshi Kinoshita ,
Naoyuki Hashimoto ,
Somei Ohnuki ,
Shinichiro Yamashita  and
Satoshi Ohtsuka
Hiroshi Oka*
Affiliation:
Faculty of Engineering, Hokkaido University, N-13, W-8, Kita-ku, Sapporo 060-8628, Japan
Yosuke Yamazaki
Affiliation:
Faculty of Engineering, Hokkaido University, N-13, W-8, Kita-ku, Sapporo 060-8628, Japan
Hiroshi Kinoshita
Affiliation:
Faculty of Engineering, Hokkaido University, N-13, W-8, Kita-ku, Sapporo 060-8628, Japan
Naoyuki Hashimoto
Affiliation:
Faculty of Engineering, Hokkaido University, N-13, W-8, Kita-ku, Sapporo 060-8628, Japan
Somei Ohnuki
Affiliation:
Faculty of Engineering, Hokkaido University, N-13, W-8, Kita-ku, Sapporo 060-8628, Japan
Shinichiro Yamashita
Affiliation:
O-arai Research and Development Center, JAEA, O-arai, Ibaraki 311-1393, Japan
Satoshi Ohtsuka
Affiliation:
O-arai Research and Development Center, JAEA, O-arai, Ibaraki 311-1393, Japan
*
*Corresponding author: [email protected]
Get access

Abstract

Oxide dispersion strengthened austenitic stainless steel (ODS316), which is based on advanced SUS316 steel, has been developed by mechanically alloying and hot extrusion. Hafnium and titanium were added to make a fine distribution of oxide particles. The stability of oxide particles dispersed in ODS316 under irradiation was evaluated after 250 keV Fe+ irradiation up to high doses at 500 °C. TEM observation and EDS analysis indicated that fine complex oxide particles with Y, Hf and Ti were mainly dispersed in the matrix. There are no significant changes in the distribution and the size of oxide particles after irradiation. It was also revealed that the constitution ratio of Ti in complex oxide appeared to be decreased after irradiation. This diffuse-out of Ti during irradiation could be explained by the difference in oxide formation energy among alloying elements.

Keywords

nuclear materialsmicrostructuretransmission electron microscopy (TEM)
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1298: Symposium Q/R/T – Advanced Materials for Applications in Extreme Environments , 2011 , mrsf10-1298-q03-03
Copyright
Copyright © Materials Research Society 2011

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1. Uchida, Y., Ohnuki, S., Hashimoto, N., Suda, T., Nagai, T., Shibayama, T., Hamada, K., Akasaka, N., Yamashita, S., Ohstuka, S., and Yoshitake, T., Mater. Res. Soc. Symp. Proc. 981 (2007).Google Scholar
2. Ukai, S., Mizuta, S., Yoshitake, T., Okuda, T., Fujiwara, M., Hagi, S., Kobayashi, T., J.Nucl.Mater., 283-287 (2000) 702–706.Google Scholar
3. Shibahara, I., Ukai, S., Onose, S., Shikakura, S., J. Nucl. Mater. 204 (1993) 131.Google Scholar
4. Yamashita, S., Ohstuka, S., Akasaka, N., Ukai, S., and Ohnuki, S., Phil. Mag. Lett. 525-529 (2004) 84.Google Scholar