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Current Status of Large Helical Device and Its Prospect for Deuterium Experiment

M. Osakabe, Y. Takeiri, T. Morisaki, G. Motojima, K. Ogawa, M. Isobe, M. Tanaka, S. Murakami, A. Shimizu, K. Nagaoka, H. Takahashi, K. Nagasaki, H. Takahashi, T. Fujita, Y. Oya, M. Sakamoto, Y. Ueda, T. Akiyama, H. Kasahara, S Sakakibara, R. Sakamoto, M. Tokitani, H. Yamada, M. Yokoyama, Y. Yoshimura, LHD Experiment Group

Fusion Science and Technology / Volume 72 / Number 3 / October 2017 / Pages 199-210

Technical Paper / dx.doi.org/10.1080/15361055.2017.1335145

Received:October 2, 2016
Accepted:January 23, 2017
Published:August 25, 2017

Achievement of reactor relevant plasma condition in Helical type magnetic devices and exploration in its related plasma physics and fusion engineering are the aim of the Large Helical Device (LHD) project. In the recent experiments on LHD, we have achieved ion-temperature of 8.1 keV at 1 × 1019 m−3 by the optimization of wall conditioning using long pulse discharge by Ion Cyclotron Heating (ICH). The electron temperature of 10 keV at 1.6 × 1019 m−3 was also achieved by the optimization of Electron Cyclotron Heating (ECH). For further improvement in plasma performance, the upgrade of the Large Helical Device (LHD), including the deuterium experiment, is planned. In this paper, the recent achievements on LHD and the upgrade of LHD are described.