Zobrazeno 1 - 10
of 82
pro vyhledávání: '"Masato Akiba"'
Autor:
Koichiro Ezato, M. Tokitani, T. Hotta, Suguru Masuzaki, Masato Akiba, Mikio Enoeda, Akira Kurumada, Katsumasa Nakamura, S. Suzuki, Kazutoshi Tokunaga, K. Araki, Makoto Hasegawa
Publikováno v:
Fusion Engineering and Design. 136:1624-1628
Tungsten coating with a thickness of 1 mm on reduced-activation ferritic/martensitic steel (RAF/M) F82H (Fe-8Cr-2W), which is a leading structural material candidate for DEMO, have been produced by Atmospheric Plasma Spraying (APS) and Vacuum Plasma
Publikováno v:
Fusion Engineering and Design. 89:1280-1283
Lithium titanate (Li2TiO3) pebbles were irradiated with D3+ ions with energy of 5.0 keV, and the amounts of retained deuterium in the pebbles were measured by thermal desorption spectroscopy. In this research the irradiation/heating cycles were carri
Autor:
Yuji Nobuta, Sadaaki Suzuki, Masao Matsuyama, Masato Akiba, Tomoaki Hino, Shinsuke Abe, Satoshi Akamaru, Yuji Hatano, Yuji Yamauchi
Publikováno v:
Fusion Engineering and Design. 89:1516-1519
DT + ion irradiation was performed on polycrystalline tungsten, graphite and carbon film and both the amount of retained tritium and the reduction of retained tritium after preservation in vacuum were investigated using an IP technique and BIXS. In a
Autor:
Kenichi Hashizume, Sadaaki Suzuki, Koichiro Ezato, Teppei Otsuka, Masato Akiba, Kazutoshi Tokunaga, Mikio Enoeda, M. Higaki
Publikováno v:
Fusion Science and Technology. 67:379-381
Hydrogen diffusion coefficients in a reduced activation ferritic/martensitic steel (F82H) and an oxide dispersion strengthened F82H (ODS-F82H) have been determined from depth profiles of plasma-loa...
Autor:
Sadaaki Suzuki, K. Araki, Kazutoshi Tokunaga, Mikio Enoeda, Y. Miyamoto, Koichiro Ezato, Katsumasa Nakamura, Makoto Hasegawa, Takuya Nagasaka, T. Fujiwara, Ryuta Kasada, Masato Akiba, Akihiko Kimura, T. Hotta
Publikováno v:
Journal of Nuclear Materials. 438:S905-S908
High density W coatings on reduced activation ferritic martensitic steel (RAF/M) have been produced by Vacuum Plasma Spraying technique (VPS) and heat flux experiments on them have been carried out to evaluate their possibility as a plasma-facing arm
Autor:
Takuya Nagasaka, Koichiro Ezato, Kazuo Nakamura, Satoshi Suzuki, Kazutoshi Tokunaga, Akihiko Kimura, Mikio Enoeda, Masato Akiba, Tomohiro Hotta, Makoto Hasegawa, Y. Miyamoto, Ryuta Kasada, Teppei Otsuka, Akira Kobayashi, T. Fujiwara, K. Araki
Publikováno v:
QUARTERLY JOURNAL OF THE JAPAN WELDING SOCIETY. 31:183s-187s
Autor:
Yoshinori Kawamura, Kazuhiro Kobayashi, Masaru Nakamichi, Keitaro Kondo, Kentaro Ochiai, Toshihiko Yamanishi, Yasunori Iwai, Takumi Hayashi, Tsuyoshi Hoshino, Chikara Konno, Masato Akiba
Publikováno v:
Fusion Engineering and Design. 87:1253-1257
In a fusion reactor, the prediction of tritium release behavior from breeder blanket is important to design the tritium recovery system, but the amount of tritium generated is necessary information to do that. Hence, tritium generation and recovery s
Autor:
Satoshi Akamaru, Satoshi Suzuki, Tomoaki Hino, Masato Akiba, Yuji Nobuta, Yuji Hatano, Yuji Yamauchi, Masao Matsuyama
Publikováno v:
Fusion Engineering and Design. 87:1070-1073
Co-deposited carbon film with different deuterium concentration, D/C, were exposed to tritium gas at the temperature of 423 K, and then the atomic ratio of absorbed tritium to carbon, T/C, was evaluated. The obtained data were discussed with crystal
Autor:
Yuji Hatano, Yuji Yamauchi, Tomoaki Hino, S. Suzuki, Masao Matsuyama, Y. Nobutaa, Masato Akiba, Satoshi Akamaru
Publikováno v:
Fusion Science and Technology. 60:1535-1538
Tritium retention in plasma facing materials is a primary issue for ITER and next step fusion devices, since it greatly affects its safety and operational schedule. In the ITER, carbon and tungsten...
Autor:
Ken Tokunaga, Masato Akiba, Koichiro Ezato, Sadaaki Suzuki, Tetsuo Tanabe, Naoaki Yoshida, Teppei Otsuka
Publikováno v:
Journal of Nuclear Materials. 417:1135-1138
Hydrogen including a trace amount of tritium was loaded on the edge surface of an F82H rod. After the loading, the rod was held at 298 or 323 K to allow hydrogen diffuse in and release out. Tritium tracer techniques have been applied to determine hyd