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

doi:10.1016/j.jnucmat.2015.06.057

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 journal › Article › peer-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 language	English
Pages (from-to)	835-839
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	465
DOIs	https://doi.org/10.1016/j.jnucmat.2015.06.057
Publication status	Published - 2015 Oct 1
Externally published	Yes

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

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.",

keywords = "Gen. IV nuclear reactor, Ion irradiation, Ni-base ODS alloy, Resistance to He embrittlement",

author = "Naoko Oono and Shigeharu Ukai and Sosuke Kondo and Okinobu Hashitomi and Akihiko Kimura",

year = "2015",

month = oct,

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doi = "10.1016/j.jnucmat.2015.06.057",

language = "English",

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T1 - Irradiation effects in oxide dispersion strengthened (ODS) Ni-base alloys for Gen. IV nuclear reactors

AU - Oono, Naoko

AU - Ukai, Shigeharu

AU - Kondo, Sosuke

AU - Hashitomi, Okinobu

AU - Kimura, Akihiko

PY - 2015/10/1

Y1 - 2015/10/1

N2 - 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.

AB - 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.

KW - Gen. IV nuclear reactor

KW - Ion irradiation

KW - Ni-base ODS alloy

KW - Resistance to He embrittlement

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