the ICRH Team

Max Planck Institute for Plasma Physics

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i-10 index

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The NI Team

Max Planck Institute for Plasma Physics

the ASDEX Upgrade Team

Max Planck Institute for Plasma Physics

O. Vollmer

Max Planck Society

A. Stäbler

Max Planck Society

F. Ryter

Max Planck Institute for Plasma Physics

W. Kohlhaas

Royal Military Academy

M. Kaufmann

Lucerne University of Applied Sciences and Arts

O. Gruber

Max Planck Institute for Plasma Physics

K. Krieger

Max Planck Institute for Plasma Physics

R.A. Moyer

University of California, San Diego

Cooperative Institutions

Max Planck Institute for Plasma Physics

Max Planck Society

Max Planck Innovation

University of California, San Diego

Forschungszentrum Jülich

Oak Ridge National Laboratory

University of California, Los Angeles

Fusion (United States)

Fusion Academy

National Institute for Fusion Science

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ALT-II toroidal belt pump limiter performance in TEXTOR

Journal of Nuclear Materials (1989)

Textor Team the ICRH Team Dan M. Goebel R.W. Conn W.J. Corbett

Limiter

Electron temperature

Power density

10.1016/0022-3115(89)90262-6

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Citations (37)

Boronization of ASDEX

Journal of Nuclear Materials (1990)

the ASDEX Upgrade Team the ICRH Team the JT- SA Integrated Project Team The NI Team Uwe Schneider

Ohmic contact

Carbon fibers

Glow discharge

Boron carbide

Fusion power

10.1016/0022-3115(90)90071-t

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Citations (19)

H-Mode operating regimes and confinement in ASDEX-Upgrade

Physica Scripta (1995)

F. Ryter M. Alexander C. Fuchs O. Gruber A. Kallenbach

The H-mode operating boundaries and confinement regimes in ASDEX Upgrade are described. The L to H mode threshold power is shown to linearly increase with the product of line-averaged electron density times magnetic field. The analyses of the boundaries between different ELM types show that mainly the steady-state ELMing H-mode discharges with type-I ELMs are achieved above the power threshold. The global confinement time of such discharges is analysed. Discharges of the same type with high edge radiation power (80% of the input power radiated) obtained by neon puffing remain in the H-mode and have a good confinement. The importance of strong deuterium puffing in addition to neon is demonstrated. These promising results for power load reduction of the divertor in ITER are discussed.

ASDEX Upgrade

10.1088/0031-8949/51/5/017

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Citations (6)