Tensile properties and microstructure of Zr–1.8Nb alloy subjected to 140-MeV C4+ ion irradiation

H. L. Yang, S. Kano, Y. Matsukawa, J. J. Shen, Z. S. Zhao, Z. G. Duan, D. Y. Chen, K. Murakami, Y. F. Li, Y. Satoh, H. Abe

研究成果: Article査読

12 被引用数 (Scopus)

抄録

Tensile properties and microstructure of a Zr–1.8Nb alloy subjected to 140-MeV C4+ ion irradiation at 573 K up to 5.3 dpa have been investigated by using 0.18 mm-thick tensile specimens. Irradiation damage was introduced into the tensile specimens homogeneously over entire thickness using a variable energy degrader. Irradiation-induced strengthening and embrittlement (loss of ductility) were successfully evaluated. The yield strength of irradiated specimens (3.1- and 5.3-dpa) was 137% and 145% of unirradiated specimen, whereas the total elongation of those irradiated specimens was less than a half of unirradiated specimen. It appears that the rate of embrittlement is fairly faster than the rate of strengthening. Transmission electron microscopy (TEM) observation on the 3.1-dpa specimen revealed that the bcc-Nb/Zr precipitates originally contained in the alloy were stable in terms of crystal structure and size. The size and number density of dislocation loops were 7.2 nm and 1.2 × 1021/m3 for the <a>-loops, 15.4 nm and 6.5 × 1020/m3 for the <c>-type loops, respectively. The increase of yield strength expected from these dislocation loops was ∼64% of the actual irradiation-induced strengthening, indicating that the dislocation loops are the main contributors for the irradiation-induced strengthening.

本文言語English
ページ(範囲)138-145
ページ数8
ジャーナルJournal of Nuclear Materials
495
DOI
出版ステータスPublished - 2017 11
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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