M
Masataka Nishi
Researcher at Japan Atomic Energy Research Institute
Publications - 235
Citations - 2220
Masataka Nishi is an academic researcher from Japan Atomic Energy Research Institute. The author has contributed to research in topics: Electromagnetic coil & Superconducting magnet. The author has an hindex of 22, co-authored 235 publications receiving 2124 citations. Previous affiliations of Masataka Nishi include Toshiba.
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Journal ArticleDOI
Design study of fusion DEMO plant at JAERI
Kenji Tobita,Satoshi Nishio,Mikio Enoeda,Masayasu Sato,Takaaki Isono,Shinji Sakurai,Hideo Nakamura,Satoshi Sato,Satoshi Suzuki,M. Ando,Koichiro Ezato,T. Hayashi,Takanori Hirose,Takashi Inoue,Yoshinori Kawamura,Norikiyo Koizumi,Y. Kudo,R. Kurihara,T. Kuroda,Makoto Matsukawa,K. Mouri,Y. Nakamura,Masataka Nishi,Nomoto Yasunobu,Junji Ohmori,Naoyuki Oyama,Keishi Sakamoto,T. Suzuki,M. Takechi,Hiroyasu Tanigawa,K. Tsuchiya,Daigo Tsuru +31 more
TL;DR: In this paper, three options of fusion DEMO plant are proposed characterized by functions of the center solenoid (CS), and the prime option uses a downsized CS, which does not provide sufficient V-s for plasma current ramp-up but supplies enough coil current for plasma shaping.
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Incident energy dependence of blistering at tungsten irradiated by low energy high flux deuterium plasma beams
TL;DR: In this paper, polycrystalline tungsten samples have been irradiated at near room temperature by high flux deuterium plasma beams with incident ion energies ranging 7-98 eV/D.
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Influence of blistering on deuterium retention in tungsten irradiated by high flux deuterium 10-100 eV plasmas
TL;DR: In this paper, the influence of blistering on deuterium retention in polycrystalline tungsten (W) has been studied at incident energies of tens of eV and a fixed incident flux of 1.5 × 1022 D/m2/s.
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The Water Detritiation System of the ITER Tritium Plant
Yasunori Iwai,Y. Misaki,T. Hayashi,Toshihiko Yamanishi,Satoshi Konishi,Masataka Nishi,R. Ninomiya,S. Yanagimachi,S. Senrui,Hiroshi Yoshida +9 more
TL;DR: The water detritiation system (WDS) of tritium plant for the International Thermonuclear Experimental Reactor (ITER) was designed as discussed by the authors, where the concept of the Combined Electrolysis Catalytic Exchange (CECE) was introduced.
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The tritium fuel cycle of ITER-FEAT
Manfred Glugla,A. Busigin,L. Dörr,R. Haange,T. Hayashi,O. Kveton,R. Lässer,D.K. Murdoch,Masataka Nishi,R.-D. Penzhorn,Hiroshi Yoshida +10 more
TL;DR: The design of the tritium fuel cycle has to be based upon well proven technology to assure the safe handling of Tritium along with credible accountancy, low tritiam inventory, low generation of wastes and a high reliability of all components throughout the lifetime of ITER-FEAT as mentioned in this paper.