Helium ion irradiation effects in ODS and non-ODS ferritic steels

Ryuta Kasada, Hiromasa Takahashi, Kentaro Yutani, Hirotatsu Kishimoto, Akihiko Kimura

Research output: Chapter in Book/Report/Conference proceedingChapter

1 Citation (Scopus)

Abstract

Irradiation-resistant materials R&D are one of the key issues to realize fusion power reactor because 14 MeV fusion neutrons will give severe degradation to the structural materials through significant displacement damage with a large amount of transmutation helium up to several thousand appm. When these helium atoms diffuse onto grain boundaries, it can lead to degradation of toughness through intergranular fracture. The present paper describes superior resistance of oxide dispersion strengthened (ODS) ferritic steels to the intergranular fracture due to helium. Dual-beam ion-irradiation technique was applied to reveal the helium effect on the microstructural evolution and mechanical property change of the ODS ferritic steels as well as of the non-ODS ferritic steels.

Original languageEnglish
Title of host publicationZero-Carbon Energy Kyoto 2010
Subtitle of host publicationProceedings of the Second International Symposium of Global COE Program "Energy Science in the Age of Global Warming-Toward CO2 Zero-emission Energy System"
Pages300-305
Number of pages6
DOIs
Publication statusPublished - 2011 Dec 1
Externally publishedYes

Publication series

NameGreen Energy and Technology
Volume66
ISSN (Print)1865-3529
ISSN (Electronic)1865-3537

Keywords

  • Fusion reactor
  • Helium effect
  • Ion-irradiation
  • Irradiation effect
  • Structural materials

ASJC Scopus subject areas

  • Renewable Energy, Sustainability and the Environment
  • Energy Engineering and Power Technology
  • Management, Monitoring, Policy and Law
  • Industrial and Manufacturing Engineering

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