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Kobayashi, Takayuki; Terakado, Masayuki; Sato, Fumiaki; Yokokura, Kenji; Shimono, Mitsugu; Hasegawa, Koichi; Sawahata, Masayuki; Suzuki, Sadaaki; Hiranai, Shinichi; Igarashi, Koichi; et al.
Plasma and Fusion Research (Internet), 4, p.037_1 - 037_10, 2009/08
Electron cyclotron (EC) heating and current drive (CD) are key tools to control fusion plasma especially for effective electron heating and for suppression of neoclassical tearing mode (NTM). Recently, developments of a high power gyrotron and a power modulation technique have been successfully achieved on JT-60U ECRF system in order to enhance the system performance. Stable gyrotron oscillation with oscillation power of 1.5 MW for 1 s was demonstrated in 2007, for the first time. Then temperature rise of cavity and collector has been investigated. It has been shown that the longer pulse operation with 1.5 MW by an improved 110 GHz gyrotron is possible. In addition, modulated ECCD in synchronized with NTM rotation has been performed with the oscillation power of 0.8 MW and the frequency around 5 kHz. The synchronizing system has worked very well and it has played an essential role in NTM suppression experiments on JT-60U.
Takemoto, Jumpei; Watanabe, Kazuhiro; Yamamoto, Masanori; Inoue, Takashi; Sakamoto, Keishi; Yamashita, Yasuo*
no journal, ,
no abstracts in English
Koide, Yoshihiko
no journal, ,
The result of JT-60 as the National Centralized Tokamak and the development in the future will be reported in Symposium on "Development of the domestic tokamak research after the JT-60 experiment is completed". Reported first will be the details of how the JT-60 was placed as the National Centralized Tokamak. Next will be the remarkable results of joint research, which resulted from the further emphasis on the system of management of the corporate planning and a joint research. Finally, considering that a joint research related to JT-60SA becomes a main subject after 2009, we will show the policy of continuing a joint research by changing its name to "National Centralized Tokamak Joint Research".
Moriyama, Shinichi; Kobayashi, Takayuki; Isayama, Akihiko; Yokokura, Kenji; Shimono, Mitsugu; Hasegawa, Koichi; Sawahata, Masayuki; Suzuki, Sadaaki; Terakado, Masayuki; Hiranai, Shinichi; et al.
no journal, ,
no abstracts in English
Tobari, Hiroyuki; Umeda, Naotaka; Watanabe, Kazuhiro; Inoue, Takashi; Sakamoto, Keishi; Yamashita, Yasuo*
no journal, ,
no abstracts in English
Kajiwara, Ken; Kasugai, Atsushi; Oda, Yasuhisa; Takahashi, Koji; Kobayashi, Noriyuki; Sakamoto, Keishi
no journal, ,
no abstracts in English
Mizuno, Takatoshi; Inoue, Takashi; Taniguchi, Masaki; Kashiwagi, Mieko; Umeda, Naotaka; Tobari, Hiroyuki; Watanabe, Kazuhiro; Dairaku, Masayuki; Sakamoto, Keishi
no journal, ,
no abstracts in English
Fukumoto, Masakatsu*; Yamawaki, Akifumi*; Otsuka, Yusuke*; Ueda, Yoshio*; Taniguchi, Masaki; Inoue, Takashi; Sakamoto, Keishi; Yagyu, Junichi; Arai, Takashi; Takagi, Ikuji*; et al.
no journal, ,
Tungsten is considered as a candidate material for first wall armor of DT fusion reactors. However, it is anticipated that tritium might accumulate in the damage defects that caused by neutron irradiation. The present study measured deuterim accumulation in tungsten specimen after high energy hydrogen ion beam irradiation for generation of irradiation damages and then low energy deuterium beams for their accumulation. As a result, the deuterium accumulation in irradiated tungsten was enhanced as high as six times than that of original specimen.
Oda, Yasuhisa; Kajiwara, Ken; Kobayashi, Noriyuki; Takahashi, Koji; Kasugai, Atsushi; Sakamoto, Keishi
no journal, ,
no abstracts in English
Nishiyama, Tomokazu; Okano, Fuminori; Miyo, Yasuhiko; Sasaki, Noboru*; Meguro, Masashi*; Tajika, Masaharu*; Sato, Yoji; Sato, Masayasu
no journal, ,
no abstracts in English
Hayashi, Takumi
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no abstracts in English
Saito, Ai*; Tobita, Kenji; Nishio, Satoshi; Sato, Satoshi; Enoeda, Mikio
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Based on the combined analysis with neutronics and heat transfer, blanket concept of a fusion DEMO reactor named SlimCS was studied. The study indicates that satisfying tritium self-sufficiency and heat removal simultaneously is difficult as long as water-cooled solid breeder blanket is concerned. The most highest tritium breeding ratio (TBR) was obtained for a separated arrangement with Li
TiO
pebbles and Be plates. However, this concept has a disadvantage in a complexity of the internal structure. When the mixed packing of LiTiO and Be
Ti pebbles is applied, the internal structure of blanket becomes simple but tritium self-sufficiency seems problematic adversely. Issues in these blanket study and possible solutions are presented.
Sueoka, Michiharu; Akasaka, Hiromi; Sugimura, Toru; Kawamata, Yoichi; Kurihara, Kenichi; Naito, Osamu
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no abstracts in English
Ninomiya, Hiromasa
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no abstracts in English
Kawamata, Yoichi; Naito, Osamu; Kurihara, Kenichi; Totsuka, Toshiyuki; Akasaka, Hiromi; Sueoka, Michiharu; Sugimura, Toru
no journal, ,
no abstracts in English
Suzuki, Satoshi; Ito, Tatsuya*; Nobuta, Yuji*; Yamauchi, Yuji*; Hino, Tomoaki*; Ezato, Koichiro; Yokoyama, Kenji; Akiba, Masato
no journal, ,
A reduced activation ferritic-maternstic steel, F82H, is one of candidate structural materials for the first wall of fusion machines. For F82H, retention and desorption behavior of F82H has not been clarified though such behavior is considered to be significant from the plasma density control and safety points of view. In this study, F82H samples were irradiated by hydrogen ion in JAEA. In addition, these samples with surface defects were also irradiated by deuterium ion to investigate the retention and the desorption behavior based on its surface defects. As a result, while the amount of the deuterium retention has not been changed at a holding temperature below 550 K, it is significantly decreased at a holding temperature over 770 K.
Terakado, Masayuki; Kobayashi, Takayuki; Sato, Fumiaki; Sawahata, Masayuki; Suzuki, Sadaaki; Shimono, Mitsugu; Hiranai, Shinichi; Igarashi, Koichi; Suzuki, Takashi; Wada, Kenji; et al.
no journal, ,
no abstracts in English
Yamauchi, Kunihito; Shimada, Katsuhiro; Okano, Jun; Omori, Yoshikazu; Terakado, Tsunehisa; Kurihara, Kenichi
no journal, ,
no abstracts in English
Totsuka, Toshiyuki; Sakata, Shinya; Sato, Minoru; Kiyono, Kimihiro; Naito, Osamu; Kawamata, Yoichi
no journal, ,
no abstracts in English
Shimada, Katsuhiro; Terakado, Tsunehisa; Omori, Yoshikazu; Okano, Jun; Yamauchi, Kunihito; Kurihara, Kenichi
no journal, ,
no abstracts in English
