Deuterium permeation behavior and its iron-ion irradiation effect in yttrium oxide coating deposited by magnetron sputtering

Takumi Chikada, Hikari Fujita, Jan Engels, Anne Houben, Jumpei Mochizuki, Seira Horikoshi, Moeki Matsunaga, Masayuki Tokitani, Yoshimitsu Hishinuma, Sosuke Kondo, Kiyohiro Yabuuchi, Thomas Schwarz-Selinger, Takayuki Terai, Yasuhisa Oya

Research output: Contribution to journalArticlepeer-review

11 Citations (Scopus)


Tritium permeation through structural materials is a critical issue in fusion reactors from the viewpoints of sufficient fuel balance and radiological hazard. Ceramic coatings have been investigated as tritium permeation barrier for several decades; however, irradiation effects of the coatings on permeation are not elucidated. In this work, yttrium oxide coatings were fabricated on reduced activation ferritic/martensitic steels by radio frequency magnetron sputtering, and their microstructures and deuterium permeation behaviors were investigated before and after iron-ion irradiation at different temperatures. An as-deposited coating had a columnar structure and transformed into a granular one after annealing. An amorphous layer formed near the coating-substrate interface of irradiated coatings, and its thickness became thinner with increasing irradiation temperature. Voids of approximately 20 nm in diameter also formed in the irradiated coatings. Deuterium permeation flux of the sample irradiated to 1 dpa at room temperature was the lowest among the unirradiated and irradiated samples, and a permeation reduction factor indicated up to 390. The amorphous layer disappeared after deuterium permeation measurements due to damage recovery, while the voids remained and aggregated. The irradiation damage would accelerate nucleation of the crystal, resulting in a decrease of the permeation flux.

Original languageEnglish
Pages (from-to)560-566
Number of pages7
JournalJournal of Nuclear Materials
Publication statusPublished - 2018 Dec 1
Externally publishedYes


  • Coating
  • Irradiation
  • Permeation
  • Tritium
  • Yttrium oxide

ASJC Scopus subject areas

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


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