Status and Plan of GAMMA 10 Tandem Mirror Program
| Autor: | N. Ichioka, Yousuke Nakashima, Makoto Ichimura, Yoshiaki Miyata, Masayuki Yoshikawa, M. Mizuguchi, Mao Ota, K. Hosoi, Ryuya Ikezoe, Y. Imai, Hitomi Aoki, Yasuo Yoshimura, Takashi Mutoh, F. Yaguchi, R. Yonenaga, T. Nakamura, T. Murakani, Hiroyuki Takahashi, K. Yagi, Isao Katanuma, Takashi Shimozuma, Hideaki Iizumi, Tsuyoshi Imai, Hideyuki Kondou, Keishi Sakamoto, H. Takeda, Tsuyoshi Kariya, S. Masaki, T. Ishii, T. Yokoyama, R. Minami, Shin Kubo, Yuusuke Yamaguchi, H. Ozawa |
|---|---|
| Rok vydání: | 2011 |
| Předmět: |
Physics
Nuclear and High Energy Physics Tandem 020209 energy Mechanical Engineering Nuclear engineering Cyclotron 02 engineering and technology Plan (drawing) 01 natural sciences 010305 fluids & plasmas law.invention Nuclear Energy and Engineering law 0103 physical sciences 0202 electrical engineering electronic engineering information engineering General Materials Science Spark plug Civil and Structural Engineering |
| Zdroj: | Fusion Science and Technology. 59:1-8 |
| ISSN: | 1943-7641 1536-1055 |
| DOI: | 10.13182/fst11-a11563 |
| Popis: | Recent progress and near future plan of GAMMA 10 efforts are presented. With high power plug electron cyclotron heating (ECH) up to ~ 400 kW, the ion confining potential of more than 2 kV was confirmed. The drift type low frequency fluctuations were suppressed by the positive radial electric field produced by plug ECH. It is found that the efficient EC heating on mirror devices from a strong B field side requires the minimization of the stray microwave in addition to the 100% X-mode excitation to avoid the enhancement of the ion loss. The development of a gyrotron, the key tool of these ECH experiments, has been made in collaboration with NIFS (National Institute for Fusion Science), More than 1.5 MWfor more than Is has been demonstrated at 77GHz. The plan of the boundary plasma research program with modification of GAMMA 10 is in progress. The new program includes the physics and technology studies of the divertor and SOL plasmas and PWI relevant to torus plasmas like ITER. The high heat flux experiments using the open end mirror throat has been started and we have obtained successful preliminary data, which include the heat flux of 8 MW/m2. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|