Irradiation effects in oxide dispersion strengthened (ODS) Ni-base alloys for Gen. IV nuclear reactors

Naoko Oono, Shigeharu Ukai, Sosuke Kondo, Okinobu Hashitomi, Akihiko Kimura

Research output: Contribution to journalArticlepeer-review

15 Citations (Scopus)

Abstract

Oxide particle dispersion strengthened (ODS) Ni-base alloys are irradiated by using simulation technique (Fe/He dual-ion irradiation) to investigate the reliability to Gen. IV high-temperature reactors. The fine oxide particles with less than 10 nm in average size and approximately 8.0 × 1022 m-3 in number density remained after 101 dpa irradiation. The tiny helium bubbles were inside grains, not at grain-boundaries; it is advantageous effect of oxide particles which trap the helium atoms at the particle-matrix interface. Ni-base ODS alloys demonstrated their great ability to overcome He embrittlement.

Original languageEnglish
Pages (from-to)835-839
Number of pages5
JournalJournal of Nuclear Materials
Volume465
DOIs
Publication statusPublished - 2015 Oct 1
Externally publishedYes

Keywords

  • Gen. IV nuclear reactor
  • Ion irradiation
  • Ni-base ODS alloy
  • Resistance to He embrittlement

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

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