Recovery behavior in neutron irradiated β-sic

T. Suzuki, T. Maruyama, T. Iseki, T. Mori, M. Ito

研究成果: Article査読

26 被引用数 (Scopus)

抄録

Reaction sintered β-SiC specimens were neutron-irradiated in the fast breeder reactors, JOYO, Rapsodie and Phenix, at temperatures around 430 to 550°C to a fluence from 4.0 × 1023 to 1.0 × 1027 n/m2 (E > 0.1 MeV). A change in the specimen length was accurately measured using a conventional micrometer after isochronal annealing at high temperatures. The specimens irradiated to a neutron fluence of about 1025 n/m2 showed a larger dimensional change on anneals than those irradiated to a fluence of 1026 n/m2. A change in lattice parameters by annealing was also measured. It showed that the temperature dependence is nearby identical to that of the macroscopic length change. The transmission electron microscopic study of the neutron-irradiated β-SiC specimens showed the formation of irradiation induced defects, considered to be dislocation loops. An increase in the neutron fluence resulted in the growth of the dislocation loops. The dislocation loops in strongly irradiated β-SiC interacted with each other, forming the heavily disturbed dislocation structure. The effect of the neutron fluence on the microstructure and dimendional change was discussed.

本文言語English
ページ(範囲)334-340
ページ数7
ジャーナルJournal of Nuclear Materials
149
3
DOI
出版ステータスPublished - 1987 8月
外部発表はい

ASJC Scopus subject areas

  • 核物理学および高エネルギー物理学
  • 材料科学(全般)
  • 原子力エネルギーおよび原子力工学

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