Zobrazeno 1 - 10
of 261
pro vyhledávání: '"Kenji TOBITA"'
Autor:
Ryota Nishimura, Tomohiro Seino, Keigo Yoshimura, Hiroyuki Takahashi, Akinobu Matsuyama, Kazuo Hoshino, Tetsutarou Oishi, Kenji Tobita
Publikováno v:
Plasma, Vol 7, Iss 1, Pp 64-75 (2024)
To realize the development of a long plasma source with a uniform electron density distribution in the axial direction, the spatial distribution of plasma under a multi-cusp magnetic field was analyzed using a KEIO-MARC code. Considering a cylindrica
Externí odkaz:
https://doaj.org/article/d0c0d5e983cc44eaa01ee757e6e9bc32
Autor:
Tetsutarou Oishi, Shigeru Morita, Daiji Kato, Izumi Murakami, Hiroyuki A. Sakaue, Motoshi Goto, Yasuko Kawamoto, Tomoko Kawate, Ryota Nishimura, Hiroyuki Takahashi, Kenji Tobita
Publikováno v:
Nuclear Fusion, Vol 64, Iss 10, p 106011 (2024)
Spectroscopic studies of emissions released from tungsten ions combined with a pellet injection technique have been conducted in Large Helical Device for contribution to the tungsten transport study in tungsten divertor fusion devices and for expansi
Externí odkaz:
https://doaj.org/article/136c6985b3f743cc85ede820d224c93c
Publikováno v:
AIP Advances, Vol 10, Iss 8, Pp 085018-085018-7 (2020)
A retarding field analyzer (RFA) that consists of three grids and a collector was developed, and the measurement of an ion beam that passes through plasma was demonstrated. First, a suitable grid potential structure to allow the measurement of an ion
Externí odkaz:
https://doaj.org/article/7fca0ff3747f445b9d87e661547a1ab7
Autor:
Yuki Homma, Kazuo Hoshino, Shohei Yamoto, Nobuyuki Asakura, Shinsuke Tokunaga, Akiyoshi Hatayama, Yoshiteru Sakamoto, Ryoji Hiwatari, Kenji Tobita, Joint Special Design Team for Fusion DEMO
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 323-328 (2017)
Erosion reduction of tungsten (W) divertor target is one of the most important research subjects for the DEMO fusion reactor design, because the divertor target has to sustain large fluence of incident particles, composed mainly of fuel ions and seed
Externí odkaz:
https://doaj.org/article/9c431b1d6a534646b8ae911af4083a1e
Autor:
Naito, Masayuki, Kodaira, Satoshi, Ogawara, Ryo, Tobita, Kenji, Someya, Yoji, Kusumoto, Tamon, Kusano, Hiroki, Kitamura, Hisashi, Koike, Masamune, Uchihori, Yukio, Yamanaka, Masahiro, Mikoshiba, Ryo, Endo, Toshiaki, Kiyono, Naoki, Hagiwara, Yusuke, Kodama, Hiroaki, Matsuo, Shinobu, Takami, Yasuhiro, Sato, Toyoto, Shin-ichi, Orimo, Masayuki, Naito, Satoshi, Kodaira, Ryo, Ogawara, Kenji, Tobita, Yoji, Someya, Tamon, Kusumoto, Hiroki, Kusano, Hisashi, Kitamura, Masamune, Koike, Yukio, Uchihori
Publikováno v:
Life Sciences in Space Research. 26:69-76
Geant4 Monte Carlo simulations were carried out to investigate the possible shielding materials of aluminum, polyethylene, hydrides, complex hydrides and composite materials for radiation protection in spacecraft by considering two physical parameter
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::210bf620b7f67865e4893c28ef628a97
https://repo.qst.go.jp/records/80012
https://repo.qst.go.jp/records/80012
Publikováno v:
Fusion Science and Technology. 76:246-251
The deuterium (D) permeation behavior for 1 displacement per atom Fe2+ damaged tungsten (W) was studied by the gas-driven permeation method and compared with undamaged W. The results of thermal des...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cb52e5394e5880826d49a0102acfb78e
https://doi.org/10.1080/15361055.2019.1705727
https://doi.org/10.1080/15361055.2019.1705727
Autor:
Matsuura, Hideaki, Okamoto, Ryo, Koga, Yuki, Suganuma, Takuro, Katayama, Kazunari, Otsuka, Teppei, Goto, Minoru, Nakagawa, Shigeaki, Ishitsuka, Etsuo, Tobita, Kenji, Kenji, Tobita
Publikováno v:
Fusion Engineering and Design. 146:1077-1081
Production of tritium using a high-temperature gas-cooled reactor (HTGR) has been studied for a prior engineering test with tritium handling and for the startup operation of a demonstration fusion reactor. For this purpose, the hydrogen absorption sp
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::7e46d3ca85ad89c9f08c8b0c174d091f
https://repo.qst.go.jp/records/77705
https://repo.qst.go.jp/records/77705
Autor:
Shigeaki Nakagawa, Hideaki Matsuura, Kenji Tobita, Minoru Goto, Teppei Otsuka, Yuki Koga, Takuro Suganuma, Ryo Okamoto, Etsuo Ishitsuka, Kazunari Katayama
Publikováno v:
Fusion Engineering and Design. 146:1077-1081
Production of tritium using a high-temperature gas-cooled reactor (HTGR) has been studied for a prior engineering test with tritium handling and for the startup operation of a demonstration fusion reactor. For this purpose, the hydrogen absorption sp
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d9732f189af56b1751487be06b734a4a
https://doi.org/10.1016/j.fusengdes.2019.02.009
https://doi.org/10.1016/j.fusengdes.2019.02.009
Autor:
Uto, Hiroyasu, Kakudate, Satoshi, Hiwatari, Ryoji, Someya, Yoji, Sakamoto, Yoshiteru, Asakura, Nobuyuki, Tokunaga, Shinsuke, Tobita, Kenji, Hiroyasu, Uto, Satoshi, Kakudate, Ryoji, Hiwatari, Yoji, Someya, Yoshiteru, Sakamoto, Nobuyuki, Asakura, Shinsuke, Tokunaga, Kenji, Tobita
Publikováno v:
Fusion Engineering and Design. 146:1583-1586
JA DEMO selected the vertical maintenance scheme as the primary maintenance option. In order to improve reliability of Remote Handling (RH) and plant availability, update of in-vessel transferring mechanism of the segment, pipe unit structure on main
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::167ba29631a0e988bf3c220b02957a74
https://repo.qst.go.jp/records/77693
https://repo.qst.go.jp/records/77693
Autor:
Yoshiteru Sakamoto, Joint Special Design Team for Fusion Demo, Youji Someya, Hironobu Kudo, Ryoji Hiwatari, Kenji Tobita
Publikováno v:
Fusion Engineering and Design. 146:894-897
A conceptual design of breeding blanket module with pressure tightness against in-box LOCA has been carried out, based on a pressurized water-cooled solid breeder blanket. The cooling water for DEMO is operated at the PWR water conditions of 15.5 MPa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3ce2f8dac3ff696a325832c10e04a10b
https://doi.org/10.1016/j.fusengdes.2019.01.107
https://doi.org/10.1016/j.fusengdes.2019.01.107