Innovations in the LHD divertor program

Journal Article · Sat Apr 01 04:00:00 EST 1995 · Fusion Technology

OSTI ID:219831

Ohyabu, N; Komori, A; Noda, N; Morisaki, T; Sagara, A; Suzuki, H; Watanabe, T; Motojima, O ^[1]; Takase, H ^[2]

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1. National Inst. for Fusion Science, Nagoya (Japan)
2. Toshiba Corp., Kawasaki (Japan)

Various innovative divertor concepts have been developed to improve the LHD plasma performance. They are two divertor magnetic geometries (helical divertor configurations with and without n/m=1/1 island) and two operational scenarios (confinement improvement by generating high temperature divertor plasma and simultaneous achievement of radiative cooling and H-mode-like confinement improvement). In addition, technological development of new efficient hydrogen pumping schemes are being pursued for enhancing the divertor control capability. 16 refs., 4 figs.

• OSTI ID: 219831
• Report Number(s): CONF-941182--
• Journal Information: Fusion Technology, Journal Name: Fusion Technology Vol. 27; ISSN FUSTE8; ISSN 0748-1896
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CONTROL
DIVERTORS
H-MODE PLASMA CONFINEMENT
HELIOTRON
HYDROGEN
MAGNETIC FIELD CONFIGURATIONS
PERFORMANCE
RADIATIVE COOLING
THERMAL DIFFUSION
TOKAMAK DEVICES