Home / Store / Journals / Electronic Articles / Fusion Science and Technology / Volume 46 / Number 1 / Pages 167-174
Akio Komori, Tomohiro Morisaki, Suguru Masuzaki, Mamoru Shoji, Nobuyoshi Ohyabu, Hiroshi Yamada, Kenji Tanaka, Kazuo Kawahata, Kazumichi Narihara, Shigeru Morita, Byron Jay Peterson, Ryuichi Sakamoto, Satoru Sakakibara, Osamu Motojima, LHD Experimental Group, Hajime Suzuki
Fusion Science and Technology / Volume 46 / Number 1 / Pages 167-174
Format:electronic copy (download)
A local island divertor (LID) experiment has begun in the Large Helical Device (LHD) to demonstrate improved plasma confinement, and fundamental LID functions were demonstrated in the sixth experimental campaign in 2002-2003. It was clearly shown that when an m/n = 1/1 island is generated by adding a resonant perturbation field to the LHD magnetic configuration, the particle flow is guided along the island separatrix to the backside of the island, where carbon plates are located on a divertor head. The particles recycled there are pumped out efficiently so that the line-averaged core plasma density is reduced by a factor of ~2 at the same gas puff rate, compared with non-LID discharges. Obvious improvement of the global plasma confinement was, however, not observed yet, because the discharge could not be optimized, due to a large amount of outgas from the divertor head to the core plasma. The size of the divertor head was found to be larger than the optimum one; hence, the core plasma impacted slightly on the core plasma-facing portion of the divertor head with which the core plasma was not expected to collide.
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