Irradiation-induced hardening and embrittlement of high-Cr ODS ferritic steels

J. H. Lee, R. Kasada, H. S. Cho, A. Kimura

研究成果: Conference contribution


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.

ホスト出版物のタイトルEffects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle
ホスト出版物のサブタイトル24th Volume
出版社American Society for Testing and Materials
出版ステータスPublished - 2010 1 1
イベント24th Symposium on the Effects of Radiation on Materials - Denver, CO, United States
継続期間: 2008 6 242008 6 26


名前ASTM Special Technical Publication
1513 STP


Other24th Symposium on the Effects of Radiation on Materials
国/地域United States
CityDenver, CO

ASJC Scopus subject areas

  • 材料科学(全般)


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