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

Research output: Contribution to journalArticlepeer-review

14 Citations (Scopus)


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.

Original languageEnglish
Pages (from-to)138-145
Number of pages8
JournalJournal of Nuclear Materials
Publication statusPublished - 2017 Nov
Externally publishedYes


  • Dislocation loops
  • High energy ion irradiation
  • Mechanical properties
  • Strengthening
  • Zr–Nb alloy

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering


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