Zobrazeno 1 - 10
of 62
pro vyhledávání: '"Manabu Satou"'
Autor:
Norio Kodaka, Chihiro Nakano, Takeshi Oshio, Takatomo Hirouchi, Manabu Satou, Masao Moroi, Toshiaki Oharaseki, Hiroto Matsuse
Publikováno v:
Geriatrics & Gerontology International. 22:175-176
Publikováno v:
Journal of Nuclear Materials. 417:1030-1033
The He effects on the tensile property of 316FR austenitic stainless steel was investigated by the tensile test at 650 and 750 °C for the miniature tensile specimens, which were He-implanted below 100 °C up to 5 and 30 appm and annealed at 650 and
Publikováno v:
Journal of Nuclear Materials. 417:491-494
Neutron irradiation data for the hardness and electrical resistivity of W and W–Re was obtained by JOYO, JMTR and HFIR irradiation experiments. The irradiation damage levels and temperature range were 0.15–1.0 dpa at around 500–600 °C. The eff
Autor:
Masaharu Kinno, Katsumi Hayashi, Tomohiro Ogata, Takao Tanosaki, Mizuo Sakakibara, Shigeru Ito, Manabu Satou, Katsuyoshi Yamaguchi, Akira Hasegawa, Katayose Norichika, Taiichiro Mori, Nishida Hirokazu, Koki Ichitsubo, Mikihiro Nakata, Mikio Uematsu, Mitsuru Sato, Ken-ichi Kimura, Ryoetsu Yoshino, Yusuke Fujikura
Publikováno v:
Progress in Nuclear Science and Technology. 1:28-31
Autor:
Manabu Satou, Toetsu Shishido, Takashi Tanno, K. Abe, M. Fujiwara, Akira Hasegawa, Shuhei Nogami, Jian Chao He
Publikováno v:
Journal of Nuclear Materials. :218-221
During fusion reactor operation, transmutation elements such as rhenium (Re) and osmium (Os) are produced from tungsten (W) upon neutron irradiation. Thus, the pure W becomes W–Re or W–Re–Os alloys and its physical properties gradually change.
Autor:
N. Otake, A. Yoshikawa, Manabu Satou, Akira Hasegawa, Shuhei Nogami, Yutai Katoh, Kenji Okuno, Yasuhisa Oya
Publikováno v:
Fusion Engineering and Design. 83:1490-1494
In order to evaluate the oxidation behavior and mechanism of SiC/SiC composites with conventional pyrolitic graphite interface (PyC-SiC/SiC) and advanced multilayer interface (ML-SiC/SiC) in a HCSB blanket environment, a thermal gravimetric analysis
Autor:
Takashi Tanno, Akira Hasegawa, Manabu Satou, Shuhei Nogami, Toetsu Shishido, Katsunori Abe, Jian Chao He, M. Fujiwara
Publikováno v:
MATERIALS TRANSACTIONS. 49:2259-2264
Tungsten-based model alloys were fabricated to simulate compositional changes by neutron irradiation, performed in the JOYO fast test reactor. The irradiation damage range was 0.17–1.54 dpa and irradiation temperatures were 400, 500 and 750 � C.
Autor:
Takeo Muroga, Katsunori Abe, Manabu Satou, Takeshi Hino, Tomohito Iikubo, Toshinori Chuto, Takuya Nagasaka
Publikováno v:
Journal of Nuclear Materials. :823-828
An alloy of V-4Cr-4Ti-0.15Y was fabricated by 15 kg-scale magnetic levitation melting. The oxygen level was successfully reduced to 108 wppm by slag-out of Y 2 O 3 formation on the surface of the melted ingot. Y 2 O 3 was identified as a new type of
Autor:
J.M. Chen, Takuya Nagasaka, V. M. Chernov, Atsuyuki Suzuki, Hideo Watanabe, Ken-ichi Fukumoto, Takeo Muroga, Manabu Satou, David T. Hoelzer, Bruce A. Pint, Richard J. Kurtz
Publikováno v:
Journal of Nuclear Materials. :780-787
Recent progress in the development of low activation vanadium alloys and MHD insulator coatings for a Li-self cooled blanket is reviewed. Research progress in vanadium alloys is highlighted by technology for fabricating creep tubes, comparison of the
Autor:
Manabu Satou, Toetsu Shishido, Akira Hasegawa, Katsunori Abe, Shuhei Nogami, M. Fujiwara, Takashi Tanno, Jian Chao He
Publikováno v:
MATERIALS TRANSACTIONS. 48:2399-2402
Tungsten (W) is a candidate material for Plasma facing materials of fusion reactors. During fusion reactor operation, not only irradiation damages but also transmutation elements such as rhenium (Re) and osmium (Os) are produced by neutron irradiatio