Tritium retention in nanostructured tungsten with large effective surface area

Miyuki Yajima*, Yuji Hatano, Shin Kajita, Jie Shi, Masanori Hara, Noriyasu Ohno

*この論文の責任著者

研究成果: ジャーナルへの寄稿学術論文査読

30 被引用数 (Scopus)

抄録

Tungsten specimens with fiberform nanostructure (Nano-W) were prepared by exposure to helium plasma in the divertor plasma simulator NAGDIS-II with different amounts of helium fluence. For comparison, tungsten specimens with smooth surface (Polished-W) were also prepared. Surface area of Nano-W was measured by using Brunauer, Emmet and Teller (B.E.T.) method. Tritium retention of Nano-W and Polished-W was investigated by an imaging plate (IP) and β-ray induced X-ray spectrometry (BIXS) technique exposure to mixture gas of deuterium and tritium. It was found that surface area of Nano-W was significantly larger than that of Polished-W and increased in proportion to the amount of helium irradiation. On the other hand, tritium retention showed a saturation trend when the helium fluence was higher than 5.0 × 10 25 m 2.

本文言語英語
ページ(範囲)S1142-S1145
ジャーナルJournal of Nuclear Materials
438
SUPPL
DOI
出版ステータス出版済み - 2013

ASJC Scopus 主題領域

  • 核物理学および高エネルギー物理学
  • 材料科学一般
  • 原子力エネルギーおよび原子力工学

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