Microstructure and annealing behavior of heavily neutron-irradiated β-SiC

T. Yano, T. Suzuki, T. Maruyama, T. Iseki

Research output: Contribution to journalArticle

29 Citations (Scopus)

Abstract

TEM studies were carried out on sintered β-SiC specimens which were irradiated in fast breeder reactors up to 1.0 × 1027 n/m2 (E > 0.1 MeV) at temperatures around 500°C. In SiC grains irradiated to 10 × 1025 to 10 × 1026 n/m2, unresolvable small black dots of 2 to 5 nm in size were observed. Change in microstructure occurred in the specimens irradiated to fluerices higher than 4.8 × 1026 n/m2. Clear straight line contrast of dislocations 10 to 30 nm in length was observed, which might be Frank-type interstitial dislocation loops, lying on {111} planes. The size of defects was increased with increasing neutron fluence. Postirradiation annealing of specimens resulted in an increase in size and a decrease in the number density of defects. No void was observed. It is suggested that the dislocation loops observed in this experiment are not the cause of irradiation-induced swelling of SiC.

Original languageEnglish
Pages (from-to)311-314
Number of pages4
JournalJournal of Nuclear Materials
Volume155-157
Issue numberPART 1
DOIs
Publication statusPublished - 1988 Jul 2
Externally publishedYes

Fingerprint

Neutrons
Annealing
neutrons
Defects
microstructure
Microstructure
Breeder reactors
annealing
breeder reactors
Swelling
defects
Irradiation
Transmission electron microscopy
swelling
voids
fluence
interstitials
transmission electron microscopy
irradiation
causes

ASJC Scopus subject areas

  • Electronic, Optical and Magnetic Materials

Cite this

Microstructure and annealing behavior of heavily neutron-irradiated β-SiC. / Yano, T.; Suzuki, T.; Maruyama, T.; Iseki, T.

In: Journal of Nuclear Materials, Vol. 155-157, No. PART 1, 02.07.1988, p. 311-314.

Research output: Contribution to journalArticle

Yano, T. ; Suzuki, T. ; Maruyama, T. ; Iseki, T. / Microstructure and annealing behavior of heavily neutron-irradiated β-SiC. In: Journal of Nuclear Materials. 1988 ; Vol. 155-157, No. PART 1. pp. 311-314.
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