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

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

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review


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.

Original languageEnglish
Title of host publicationEffects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle
Subtitle of host publication24th Volume
PublisherAmerican Society for Testing and Materials
Number of pages12
ISBN (Print)9780803134256
Publication statusPublished - 2010
Event24th Symposium on the Effects of Radiation on Materials - Denver, CO, United States
Duration: 2008 Jun 242008 Jun 26

Publication series

NameASTM Special Technical Publication
Volume1513 STP
ISSN (Print)0066-0558


Conference24th Symposium on the Effects of Radiation on Materials
Country/TerritoryUnited States
CityDenver, CO


  • Cr content
  • Irradiation embrittlement
  • Irradiation hardening
  • Irradiation temperature copyright © 2009 by astm international
  • Neutron irradiation
  • Oxide dispersion strengthened steel


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