S
Satoshi Nishio
Researcher at Japan Atomic Energy Research Institute
Publications - 72
Citations - 693
Satoshi Nishio is an academic researcher from Japan Atomic Energy Research Institute. The author has contributed to research in topics: Tokamak & Fusion power. The author has an hindex of 14, co-authored 72 publications receiving 676 citations.
Papers
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Journal ArticleDOI
Waste management for JAERI fusion reactors
TL;DR: In this paper, several waste management strategies were assessed in the fusion reactor design study at Japan Atomic Energy Institute (JAERI), including reinforced neutron shield to clear the massive ex-shielding components from regulatory control, low aspect ratio tokamak to reduce the total waste, reuse of liquid metal breeding material and neutron shield.
Journal ArticleDOI
Fracture mechanics evaluation of a crack generated in SiC/SiC composite first wall
TL;DR: In this paper, a finite element analysis was carried out for the blanket first wall made of SiC/SiC composite material for the future Tokamak fusion power reactor DREAM, which is conceptually designed in the Japan Atomic Energy Research Institute.
Journal ArticleDOI
The JT-60 tokamak machine
M. Ohta,Tetsuya Abe,N. Akino,T. Ando,Takashi Arai,N. Hitomi,Hajime Hiratsuka,Tomoyoshi Horie,N. Hosogane,T. Iijima,M. Isaka,M. Kaneko,Kozo Kawasaki,K. Kodama,T. Koike,T. Kuroda,K. Matsuo,Y. Miyo,Y. Murakami,Hideo Nakamura,Y. Nakamura,Satoshi Nishio,T. Nishiyama,S. Noshiroya,Kenjiro Obara,Norio Ogiwara,M. Ohkubo,K. Ohtsu,H. Okumura,T. Ozeki,M. Seimiya,M. Shimizu,Y. Serizawa,H. Sunaoshi,M. Suzuki,Hideyuki Takatsu,N. Toyoshima,H. Urakawa,Yamamoto Masahiro,K. Yano +39 more
TL;DR: The JT-60 tokamak as discussed by the authors was the first to achieve successful operation in the JTKamak system and was used for the first time in 1985.
Patent
First wall/breeding blanket
Junichi Adachi,Ryoichi Kurihara,Satoshi Nishio,Yasushi Seki,Shuzo Ueda,Seiichiro Yamazaki,潤一 安達,誠一郎 山崎,良一 栗原,脩三 植田,敏 西尾 +10 more
TL;DR: In this article, the authors proposed a simplified cooling system for a first wall and a blanket container to remove a heat of a heat load from a plasma by the wall, and further allow a cooling material gas to uniformly flow through a neutron multiplying material and a tritium breeding material.
Journal ArticleDOI
The concept of drastically easy maintenance (DREAM) tokamak reactor
TL;DR: In this paper, a torus structure consisting of a shield integrated vacuum vessel, a divertor structure and a tritium fuel breeding blanket structure is replaced from the transverse (toroidal) direction.