TY - GEN
T1 - Irradiation-induced hardening and embrittlement of high-Cr ODS ferritic steels
AU - Lee, J. H.
AU - Kasada, R.
AU - Cho, H. S.
AU - Kimura, A.
PY - 2010/1/1
Y1 - 2010/1/1
N2 - 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.
AB - 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.
KW - Cr content
KW - Irradiation embrittlement
KW - Irradiation hardening
KW - Irradiation temperature copyright © 2009 by astm international
KW - Neutron irradiation
KW - Oxide dispersion strengthened steel
UR - http://www.scopus.com/inward/record.url?scp=77954356011&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=77954356011&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:77954356011
SN - 9780803134256
T3 - ASTM Special Technical Publication
SP - 164
EP - 175
BT - Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle
PB - American Society for Testing and Materials
T2 - 24th Symposium on the Effects of Radiation on Materials
Y2 - 24 June 2008 through 26 June 2008
ER -