Recovery of neutron-irradiation-induced defects of Al2O3, Y2O3, and yttrium-aluminum garnet

Toyohiko Yano, Hiroshi Konishi, Saishun Yamazaki, Mohd Idzat Idris, Katsumi Yoshida

Research output: Contribution to journalArticle

1 Citation (Scopus)

Abstract

SiC fiber-reinforced SiC matrix composites (SiCf/SiC) are considered as one of the candidates for blanket materials in future fusion reactors and as an advanced fuel cladding material for next-generation fission reactors. Generally, the densification of SiC needs sintering additives and oxides such as Al2O3, Y2O3, and yttrium-aluminum garnet (YAG, Y3Al5O12), which are frequently added to SiC. However, the effects of neutron irradiation on sintering additives are still unclear. In this study, we performed the neutron irradiation of Al2O3, Y2O3, and YAG at fluences up to 2.0–2.5 × 1024 n/m2 (E > 0.1 MeV) at 60–90 °C. The isochronal recovery of the macroscopic volume of Al2O3 against annealing temperature showed smooth and continuous shrinkage at a temperature of up to 1200 °C, and the volume slightly increased above that temperature. In contrast, the volume of Y2O3 showed quick shrinkage at the low temperature range, and slower and smooth recovery was observed up to ∼1100 °C. In the case of YAG, the recovery of volume occurred in a step-wise manner at 600–750 °C, and continuous shrinkage occurred at temperatures lower and higher than that temperature range. The activation energies for the macroscopic volume recoveries of three oxides were obtained from the Arrhenius plots of the rate coefficients. Two-stage recovery was observed for Al2O3, whereas more complicated recovery processes were suggested for Y2O3 and YAG.

Original languageEnglish
Pages (from-to)891-898
Number of pages8
JournalJournal of Nuclear Science and Technology
Volume54
Issue number8
DOIs
Publication statusPublished - 3 Aug 2017

Fingerprint

Neutron irradiation
neutron irradiation
Garnets
Yttrium
yttrium-aluminum garnet
recovery
Aluminum
Recovery
Defects
defects
shrinkage
Temperature
sintering
Sintering
Arrhenius plots
Oxides
temperature
oxides
fusion reactors
blankets

Keywords

  • activation energy
  • AlO, YO
  • defect recovery
  • neutron irradiation
  • yttrium-aluminum garnet (YAG)

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

Cite this

Recovery of neutron-irradiation-induced defects of Al2O3, Y2O3, and yttrium-aluminum garnet. / Yano, Toyohiko; Konishi, Hiroshi; Yamazaki, Saishun; Idris, Mohd Idzat; Yoshida, Katsumi.

In: Journal of Nuclear Science and Technology, Vol. 54, No. 8, 03.08.2017, p. 891-898.

Research output: Contribution to journalArticle

Yano, Toyohiko ; Konishi, Hiroshi ; Yamazaki, Saishun ; Idris, Mohd Idzat ; Yoshida, Katsumi. / Recovery of neutron-irradiation-induced defects of Al2O3, Y2O3, and yttrium-aluminum garnet. In: Journal of Nuclear Science and Technology. 2017 ; Vol. 54, No. 8. pp. 891-898.
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