Advanced divertor concepts

Journal Article · Tue Dec 31 04:00:00 EST 1996 · Fusion Technology

OSTI ID:447396

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

---

1. National Inst. for Fusion Science, Nagoya (Japan)

LHD divertor development program has generated various innovative divertor concepts and technologies which will help to improve the plasma performance in both helical and tokamak devices. They are two divertor operational scenarios (confinement improvement by generating high temperature divertor plasma and simultaneous achievement of radiative cooling and H-mode-like confinement improvement). Local island divertor geometry has also been proposed. This new divertor has been successfully tested in the CHS device and is planned to be installed in the LHD device. In addition, technological development of new efficient hydrogen pumping schemes (carbon sheet pump and membrane pump) are being pursued for enhancement of the divertor control capability. 17 refs., 8 figs.

• OSTI ID: 447396
• Report Number(s): CONF-9606116--
• Journal Information: Fusion Technology, Journal Name: Fusion Technology Journal Issue: 3 Vol. 30; ISSN FUSTE8; ISSN 0748-1896
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CARBON
CONTROL SYSTEMS
DESIGN
DIVERTORS
H-MODE PLASMA CONFINEMENT
HELICAL CONFIGURATION
HYDROGEN
ITER TOKAMAK
PLASMA DENSITY
PUMPING
RADIATIVE COOLING