Zobrazeno 1 - 10
of 76
pro vyhledávání: '"Yamato Asakura"'
Publikováno v:
Journal of Nuclear Science and Technology. 49:1018-1027
In order to realize the planned deuterium plasma experiments using the Large Helical Device, the National Institute for Fusion Science (NIFS) is planning to install a system for tritium recovery from exhaust gas. While adopting typical tritium recove
Autor:
Yamato Asakura, Kenji Okuno, Yasuhisa Oya, Tatsuhiko Uda, Masahiro Tanaka, S. Takami, H. Ogawa
Publikováno v:
Fusion Science and Technology. 60:1363-1366
In order to perform deuterium plasma experiments by using the Large Helical Device (LHD),the NIFS is planning to install a system for tritium recovery from exhaust gas. NIFS is planning to apply the latest technologies for tritium recovery. Oxidized
Publikováno v:
Fusion Science and Technology. 60:944-947
Autor:
Sachiko Suzuki, Kenji Okuno, Toshihiko Yamanishi, Yasuhisa Oya, Masao Matsuyama, Takumi Hayashi, Yamato Asakura
Publikováno v:
Journal of Nuclear Materials. 417:1154-1157
The ion fluence dependence of deuterium retention in SS-316 during oxidation at a temperature of 673 K was studied to evaluate the dynamics of deuterium retention in the oxide layer of SS-316. The correlation between the chemical state of stainless s
Publikováno v:
Nuclear Engineering and Design. 241:2398-2410
In PWR primary coolant, it has been assumed that Li and B ions deposited on fuel rod surface under sub-cooled boiling conditions and they changed their chemical forms by chemical reaction with nickel iron oxides on the fuel surface. Accumulated boron
Autor:
Wanjing Wang, Yamato Asakura, Yasuhisa Oya, Makoto Kobayashi, Masao Matsuyama, Toshihiko Yamanishi, Takumi Hayashi, Rie Kurata, Kenji Okuno
Publikováno v:
Fusion Science and Technology. 60:403-406
The trapping and release mechanisms of hydrogen isotopes for the stainless steel (SS) oxidized at various temperatures were investigated. The oxide layer was mainly consisted of iron oxides (FexOy)...
Autor:
Tatsuhiko Uda, Ion Cristescu, Ichiro Yamamotoa, L. Dörr, Stefan Welte, Masahiro Tanaka, Takahiko Sugiyama, R. Michling, Yamato Asakura
Publikováno v:
Fusion Science and Technology. 56:861-866
The research for the performance improvement of the Liquid Phase Chemical Exchange (LPCE) column has been carried out at Nagoya University in collaboration with National Institute for Fusion Science (NIFS) and Tritium Laboratory Karlsruhe (TLK). Koge
Design of Gaseous Tritium Recovery System Applying Commercially Available Membrane-Type Dehumidifier
Autor:
Kenji Okuno, Satoshi Fukada, Yasuhisa Oya, Hideki Ogawa, Shigeyuki Takami, Yamato Asakura, Masahiro Tanaka, Tatsuhiko Uda
Publikováno v:
Journal of Nuclear Science and Technology. 46:641-647
In order to realize the planned deuterium plasma experiments using the large helical device (LHD), the National Institute for Fusion Science (NIFS) is planning to install a system for tritium recovery from exhaust gas. While adopting typical tritium
Publikováno v:
Fusion Science and Technology. 48:480-483
Recovery of tritium released into a working area in a nuclear fusion plant is a key issue of safety. The catalytic oxidation of isotopic hydrogen including tritium is a conventional method for removing tritium from the air of the room. If a tritium r
Publikováno v:
Fusion Science and Technology. 48:405-408
A previously developed analyzer for detecting extremely small concentrations of hydrogen in air was evaluated by using it to distinguish hydrogen isotopes. The analyzer utilizes the functions of a gas chromatograph and an atomic absorption spectropho