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Takahashi, Koji; Kajiwara, Ken; Oda, Yasuhisa; Kasugai, Atsushi; Sakamoto, Keishi
no journal, ,
no abstracts in English
Kamiya, Kensaku; Fujita, Takaaki; Kojima, Atsushi; Kubo, Hirotaka
no journal, ,
Zeeman polarimetry system has been developed for the edge current density measurement in the JT-60U tokamak. The diagnostic has 20-ch viewing chords covering the plasma peripheral region with a spatial resolution of 1cm. Li-beam injection with beam current of up to 5mA has been achieved. The edge current density profile with the local peak at r/a 0.9 has been identified in the H-mode plasma, which is correlated with large pressure gradient in the pedestal region.
Sueoka, Michiharu; Akasaka, Hiromi; Yamaguchi, Taiji; Kawamata, Yoichi; Naito, Osamu
no journal, ,
no abstracts in English
Takizuka, Tomonori
no journal, ,
no abstracts in English
Matsunaga, Go; Takechi, Manabu; Sakurai, Shinji; Ide, Shunsuke; Oyama, Naoyuki; Matsukawa, Makoto; Aiba, Nobuyuki; Urano, Hajime; Sakasai, Akira; Kamada, Yutaka; et al.
no journal, ,
no abstracts in English
Oda, Yasuhisa; Kajiwara, Ken; Takahashi, Koji; Kasugai, Atsushi; Sakamoto, Keishi
no journal, ,
no abstracts in English
Kobayashi, Takayuki; Isayama, Akihiko; Hasegawa, Koichi; Suzuki, Sadaaki; Hiranai, Shinichi; Sato, Fumiaki; Wada, Kenji; Shibayama, Minoru; Yokokura, Kenji; Moriyama, Shinichi
no journal, ,
no abstracts in English
Yamaguchi, Toshikazu; Oda, Yasuhisa; Kajiwara, Ken; Takahashi, Koji; Kasugai, Atsushi; Komurasaki, Kimiya*; Sakamoto, Keishi
no journal, ,
no abstracts in English
Sato, Shoichi*; Ichimura, Makoto*; Yamaguchi, Yusuke*; Katano, Makoto*; Imai, Yasutaka*; Murakami, Tatsuya*; Miyake, Yuichiro*; Yokoyama, Takuro*; Moriyama, Shinichi; Kobayashi, Takayuki; et al.
no journal, ,
Ion cyclotron emissions (ICEs) due to deuterium-deuterium fusion-product (FP) ions on JT-60U are studied. ICE due to H-ions is identified from the difference of the toroidal wave number of 2nd ICE(D). The parameter dependence for the appearance of ICE(H) is investigated from the experimental conditions and also is studied by using "Escape Particle Orbit analysis Code (EPOC)".
Isayama, Akihiko; Kobayashi, Takayuki; Moriyama, Shinichi; Sawahata, Masayuki; Suzuki, Sadaaki; Yokokura, Kenji; Shimono, Mitsugu; Hasegawa, Koichi; Terakado, Masayuki; Hiranai, Shinichi; et al.
no journal, ,
no abstracts in English
Kawashima, Hisato; Hoshino, Kazuo; Shimizu, Katsuhiro; Takizuka, Tomonori; Ide, Shunsuke; Asakura, Nobuyuki; Sakurai, Shinji; Higashijima, Satoru; Nakano, Tomohide
no journal, ,
The divertor configuration of the super advanced tokamak device JT-60SA, which will aim the high beta steady-state operation (100 sec) with 41 MW heating power, is almost decided. Using the divertor code SONIC, the heat and particle controllability in the divertor is evaluated with assuming the equilibriums at high-density high beta, full non-inductive current drive and ITER-like operations. For the high-density high beta plasmas, it shows that the divertor condition from attachment to detachment is controllable by the combinations of gas puffing and divertor pumping. Heat load on the divertor target at the full current drive plasmas can be reduced below the allowable level of 15 MW/m
by introduction of the Ar impurity. High performance for the heat and particle control on the ITER-like plasmas is also demonstrated in the equipping device capability such as the divertor pumping with the pumping speed below 100 m
/s.
Kajiwara, Ken; Kasugai, Atsushi; Oda, Yasuhisa; Takahashi, Koji; Sakamoto, Keishi
no journal, ,
no abstracts in English
Moriyama, Shinichi; Isayama, Akihiko; Kobayashi, Takayuki; Sawahata, Masayuki; Suzuki, Sadaaki; Terakado, Masayuki; Hiranai, Shinichi; Hasegawa, Koichi; Shimono, Mitsugu; Yokokura, Kenji; et al.
no journal, ,
no abstracts in English
Matsukawa, Makoto; Shimada, Katsuhiro; Suzuki, Takahiro; Terakado, Tsunehisa; Yamauchi, Kunihito
no journal, ,
no abstracts in English
Kurita, Genichi; Tobita, Kenji; Asakura, Nobuyuki; Aiba, Nobuyuki; Nagashima, Keisuke
no journal, ,
It is necessary to obtain the stable high beta plasma in order to realize the economically superior magnetically confined fusion reactor. In these analyses, we mainly investigate the effect of plasma pressure pedestal near plasma edge region considering the bootstrap current effect due to edge plasma pressure pedestal. The following results are obtained. Increase of edge plasma pressure induces a rise of critical beta because of reduction of internal plasma pressure gradient, until the edge plasma pressure gradient and bootstrap current induces the new instability near the plasma edge. For comparatively peaked plasma pressure profiles, we have another higher door-knob like stable region near the maximum critical beta region.
Sakamoto, Yoshiteru; Araki, Masanori; BA-JA Implementing Agency*; BA-EU Implementing Agency*
no journal, ,
BA-IFERC project coordinates DEMO design activity in order to promote early realization of DEMO. At the phase one, the activity is done by workshop and /or meeting in order to discuss the role of DEMO, design issues, requirements and so on. Although there is gap in the strategy on fusion development, it is confirmed that the almost technical issues are common between EU and JA implementing Agencies. Based on these discussions, joint activities will launch from 2010. In this presentation, we will report the present status and future plan of BA-DEMO design activity.
Shiraishi, Junya; Tokuda, Shinji*
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no abstracts in English
Shinto, Katsuhiro; Wada, Motoi*; Imakita, Shinsuke*; Kaneko, Osamu*; Tsumori, Katsuyoshi*
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no abstracts in English
Uto, Hiroyasu; Tobita, Kenji; Isono, Takaaki; Hasegawa, Mitsuru*; Asakura, Nobuyuki
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no abstracts in English
Honda, Mitsuru
no journal, ,
no abstracts in English