Tritium retention in nanostructured tungsten with large effective surface area

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

doi:10.1016/j.jnucmat.2013.01.252

Tritium retention in nanostructured tungsten with large effective surface area

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

^*Corresponding author for this work

Hydrogen Isotope Research Center, Organization for Promotion of Research

Research output: Contribution to journal › Article › peer-review

30 Scopus citations

Abstract

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.

Original language	English
Pages (from-to)	S1142-S1145
Journal	Journal of Nuclear Materials
Volume	438
Issue number	SUPPL
DOIs	https://doi.org/10.1016/j.jnucmat.2013.01.252
State	Published - 2013

ASJC Scopus subject areas

Nuclear and High Energy Physics
General Materials Science
Nuclear Energy and Engineering

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@article{b03045fc89704202bf3ab466d746ebae,

title = "Tritium retention in nanostructured tungsten with large effective surface area",

abstract = "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.",

author = "Miyuki Yajima and Yuji Hatano and Shin Kajita and Jie Shi and Masanori Hara and Noriyasu Ohno",

note = "Funding Information: This work was supported by Kakenhi on Priority Areas, 476, Tritium for Fusion, from MEXT, Japan and the Collaboration Research Programs of National Institute of Fusion Science, Japan ( NIFS11KUHR013 ). ",

year = "2013",

doi = "10.1016/j.jnucmat.2013.01.252",

language = "英語",

volume = "438",

pages = "S1142--S1145",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

number = "SUPPL",

}

TY - JOUR

T1 - Tritium retention in nanostructured tungsten with large effective surface area

AU - Yajima, Miyuki

AU - Hatano, Yuji

AU - Kajita, Shin

AU - Shi, Jie

AU - Hara, Masanori

AU - Ohno, Noriyasu

N1 - Funding Information: This work was supported by Kakenhi on Priority Areas, 476, Tritium for Fusion, from MEXT, Japan and the Collaboration Research Programs of National Institute of Fusion Science, Japan ( NIFS11KUHR013 ).

PY - 2013

Y1 - 2013

N2 - 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.

AB - 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.

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U2 - 10.1016/j.jnucmat.2013.01.252

DO - 10.1016/j.jnucmat.2013.01.252

M3 - 学術論文

AN - SCOPUS:84882773725

SN - 0022-3115

VL - 438

SP - S1142-S1145

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - SUPPL

ER -

Tritium retention in nanostructured tungsten with large effective surface area

Abstract

ASJC Scopus subject areas

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