Impurity control and helium exhaust experiment in JT-60

T. Sugie, K. Itami, H. Nakamura, H. Kubo, K. Tobita, Y. Koide, A. Sakasai, T. Hirayama, M. Shimada, T. Ando, K. Annou, T. Aoyagi, T. Arai, K. Arakawa, M. Azumi, T. Fujii

研究成果: 書籍の章/レポート/Proceedings会議への寄与査読

4 被引用数 (Scopus)

抄録

Impurity characteristics have been investigated in high power (20 MW) NB heated discharges of outer and lower X-point configurations with TiC coated molybdenum or graphite first walls. The light impurity concentrations and Zeff had the lowest values in the outer X-point discharges with TiC coated molybdenum first walls. In high density discharges, the heat load on the divertor plate was suppressed by radiative cooling originating from carbon and hydrogen in the divertor region. To simulate the behaviour of the helium ash in a fusion reactor, helium particles were fuelled by a 30 keV helium beam or gas puffing in NB heated hydrogen plasmas. The neutral pressures of helium and hydrogen in the divertor region were proportional to n̄e3. For the helium transport in the main plasma, the inward flow pinch of helium ions was slightly more pronounced than that of the hydrogen ions.

本文言語英語
ホスト出版物のタイトルProc 13 Int Conf Plasma Phys Controlled Nucl Fusion Res
出版社Publ by IAEA
ページ385-392
ページ数8
ISBN(印刷版)9201300913
出版ステータス出版済み - 1991

出版物シリーズ

名前Proc 13 Int Conf Plasma Phys Controlled Nucl Fusion Res

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