Journal Published Online: 07 July 2009
Volume 6, Issue 8

Irradiation-Induced Hardening and Embrittlement of High-Cr ODS Ferritic Steels

CODEN: JAIOAD

Abstract

The dependence of irradiation temperature, neutron dose, and Cr content on irradiation hardening and embrittlement has been investigated for oxide dispersion strengthened (ODS) ferritic steels irradiated from 290 to 600°C up to the maximum neutron dose of 0.75 dpa. Irradiation hardening and embrittlement of the materials strongly depend on the irradiation temperature. While neutron dose increases from 0.01 to 0.21 dpa, the ODS steels with Al show a saturation of irradiation hardening but the no-Al ODS steel has an increase in the hardening. The higher the Cr content, the more significant the irradiation hardening and embrittlement of ODS steels irradiated below 420°C. Interestingly, the ODS ferritic steels exposed to neutrons show little change of tensile elongation, compared to 9Cr JLF-1. Furthermore the ductile-brittle transition temperature (DBTT) shift of ODS steels increases with the increasing irradiation hardening, indicating that the increase of yield strength due to radiation induced hardening increases the DBTT and thus a reduction of hardening is effective to reduce the DBTT shift.

Author Information

Lee, J.
Institute of Advanced Energy, Kyoto Univ., Kyoto, Uji, Japan
Kasada, R.
Institute of Advanced Energy, Kyoto Univ., Kyoto, Uji, Japan
Cho, H.
Institute of Advanced Energy, Kyoto Univ., Kyoto, Uji, Japan
Kimura, A.
Institute of Advanced Energy, Kyoto Univ., Kyoto, Uji, Japan
Pages: 8
Price: $25.00
Related
Reprints and Permissions
Reprints and copyright permissions can be requested through the
Copyright Clearance Center
Details
Stock #: JAI101952
ISSN: 1546-962X
DOI: 10.1520/JAI101952