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Kamiya, Kensaku; Sakamoto, Yoshiteru; Matsunaga, Go; Kojima, Atsushi; Urano, Hajime; Oyama, Naoyuki; Koide, Yoshihiko; Kamada, Yutaka; Ida, Katsumi*
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A complex multistage transition of the edge radial electric field is observed in JT-60U ELM-free H-mode phase. An interesting feature is that the poloidal rotation velocity of the carbon impurity ions changes in the later H-phase without a comparable change in the main ion pressure gradient, indicating a change in the parallel momentum and particle balance channel.
Tanimoto, Tsuyoshi; Sakaki, Hironao; Nishiuchi, Mamiko; Fukuda, Yuji; Hori, Toshihiko; Nishio, Katsuhisa; Kondo, Kiminori
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no abstracts in English
Miyato, Naoaki; Scott, B. D.*
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Reduced models such as the gyrokinetic model are constructed by the phase space transformation from the particle phase space to the guiding-centre phase space which separates the fast gyro-motion of a particle from the other dynamics. We clarify the relation between usual particle fluid moments and fluid moments in a reduced model with large flow which we have constructed recently and compare it with the standard gyrokinetic case. In particular, we discuss the push-forward representation of particle density or the reduced quasi-neutrality condition.
Tobita, Kenji
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no abstracts in English
Takizuka, Tomonori
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Kobayashi, Takayuki; Isayama, Akihiko; Hoshino, Katsumichi; Hasegawa, Koichi; Suzuki, Sadaaki; Hiranai, Shinichi; Sato, Fumiaki; Wada, Kenji; Ozeki, Masahiro; Yokokura, Kenji; et al.
no journal, ,
On the design of an antenna for the electron cyclotron heating and current drive system in JT-60SA, the reduction of risk of water leakage in vacuum is proposed by means of linear motion antenna concept. We report results of a detail study of structural, mechanical and optical design for realizing this antenna. A mock-up of the steering structure, which is the most important part of this antenna and consists of a long stroke bellows for linear motion and a bellows which is deformed when the steering shaft is rotated, was fabricated. By testing the mock-up, it was clarified that the beam injection angle range required in JT-60SA is realized by this antenna. Moreover, we confirmed that the beam profile obtained by low power measurements, in which beam angle was changed in two directions, agree with calculated profile.
plasmasMatsunaga, Go; Aiba, Nobuyuki; Shinohara, Koji; Asakura, Nobuyuki; Isayama, Akihiko; Oyama, Naoyuki; Urano, Hajime; Suzuki, Takahiro; Takechi, Manabu; Sakamoto, Yoshiteru; et al.
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no abstracts in English
Nakamura, Shigetoshi; Shibama, Yusuke; Masaki, Kei; Sakasai, Akira
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The JT-60SA project is to contribute to realization of fusion energy by supporting exploitation of ITER and by complementing ITER and engineering issues for DEMO reactors. A main component, providing vacuum insulation, radiation shield, and components' support, is cryostat. Cryostat split in two major segments; base and vessel. The base is under the manufacturing, and the vessel is still in designing. We present design status of entire cryostat and structural analysis of the top lid, which is final part to close the cryostat vessel. To achieve vacuum insulation of 10
Pa each mechanical joints' flanges of cryostat segments are lightly welded as vacuum sealing. The normal load conditions consist of; atmospheric pressure, heat load and electromagnetic force. The top lid of the cryostat is also required of the sufficient integrity and the certain stiffness to protect the sealing weldment. We present the structural integrity clarified by stress evaluation and adequate reinforcements.
Asakura, Nobuyuki; Hayashi, Takao; Ashikawa, Naoko*; Fukumoto, Masakatsu
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Isayama, Akihiko; Matsunaga, Go; Ishii, Yasutomo; Sakamoto, Yoshiteru; Moriyama, Shinichi; Kamada, Yutaka; Ozeki, Takahisa; JT-60 Team
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no abstracts in English
Uto, Hiroyasu; Tobita, Kenji; Takase, Haruhiko; Someya, Yoji; Asakura, Nobuyuki
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no abstracts in English
Kawashima, Hisato; Hoshino, Kazuo; Shimizu, Katsuhiro; Takizuka, Tomonori; Sakurai, Shinji
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Heat and particle controllability on JT-60SA divertor has been studied using the SONIC code. For the final divertor design, it has shown that requirement for heat and particle control is satisfied by using the gas puff, divertor pumping and argon impurity injection. At present, those characteristics are evaluated when the heating power is changed from 10 MW to 41 MW. With the high current plasma, the heat load changes with the power linearly, showing that the dependence is strong. We find that the edge density is strongly related with the supplied ion fluxes. For the full current drive plasma that low edge density is required, compatibility low edge density with low heat load is achieved by argon injection at 41 MW. But we find that those conditions are performed without the argon below 17 MW. Controllable regions of heat load and edge density are predicted and those give a prospect for the JT-60SA experiment.
Someya, Yoji; Tobita, Kenji; Uto, Hiroyasu; Takase, Haruhiko; Liu, C.; Asakura, Nobuyuki
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Yasumoto, Takashi*; Matsuura, Hideaki*; Shimakawa, Satoshi; Nakao, Yasuyuki*; Kochi, Shohei*; Nakaya, Hiroyuki*; Goto, Minoru; Nakagawa, Shigeaki
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no abstracts in English
Nakagawa, Atsuhiro*; Hiroyasu, Tomoyuki*; Moribayashi, Kengo; Kenmotsu, Takahiro*; Wada, Motoi*
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Tajiri, Nobuhiro*; Hiroyasu, Tomoyuki*; Wada, Motoi*; Kenmotsu, Takahiro*; Kiriyama, Hiromitsu; Daito, Izuru; Sasao, Hajime*; Suzuki, Masayuki; Okada, Hajime
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Moriyama, Shinichi; Kobayashi, Takayuki; Isayama, Akihiko; Hoshino, Katsumichi; Yokokura, Kenji; Shimono, Mitsugu; Hasegawa, Koichi; Sawahata, Masayuki; Suzuki, Sadaaki; Terakado, Masayuki; et al.
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plasma discharges of JT-60UShibata, Yoshihide*; Watanabe, Kiyomasa*; Ono, Noriyasu*; Okamoto, Masaaki*; Isayama, Akihiko; Kurihara, Kenichi; Oyama, Naoyuki; Nakano, Tomohide; Kawano, Yasunori; Matsunaga, Go; et al.
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Idomura, Yasuhiro; Jolliet, S.; Camenen, Y.*
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Linear analyzes ITG-TEM turbulence are performed by developing a kinetic electron model in a global gyrokinetic full-f Vlasov code GT5D. Through comparisons with a local flux-tube gyrokinetic code GKW, it is found that finite plasma size effects provide changes in mode structures leading to generation of residual stress. It is also shown that the residual stress changes its sign in each parameter regime where ITG modes or TEM modes are dominant. The result shows that plasma rotation driven by the residual stress may change its direction depending on the dominant modes.