The new phase of the Joint European Torus and prospects for future operation

Journal Article · Thu Jun 01 04:00:00 EDT 1995 · Physics of Plasmas

DOI:https://doi.org/10.1063/1.871487· OSTI ID:165299

Tubbing, B J.D. ^[1]

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1. JET Joint Undertaking, Abingdon, Oxon, OX143EA (United Kingdom)

The Joint European Torus (JET) [Fusion Technol. {bold 11}, 1 (1987)] restarted operations in its new pumped divertor configuration. The main elements of the new configuration are four divertor coils, an inertially cooled divertor structure, and an internal cryogenic vacuum pump. Two major differences were observed with respect to the ``old`` JET. First, the heat load capability of the divertor is dramatically improved. Second, in the high confinement mode (H mode) the occurrence of edge localized modes (ELMs), is more prevalent. Quasi-steady-state ELMy H modes are now obtained in a wide variety of conditions. In the 1994 experimental campaign maximum plasma currents of 4 MA have been obtained. Steady-state H-mode operation has been obtained for a duration of 20 s. Detached divertor operation was established in Ohmic and L-mode plasmas, but not yet in H mode. In low current discharges a poloidal beta {beta}{sub {ital P}}=2.6 has been obtained in transient. The high {beta}{sub {ital P}} regime has been extended to long pulse ELMy H mode. Preliminary experiments have not shown an effect of magnitude shear reversal on the confinement. Using the new internal saddle coils, powered by high-frequency amplifiers, toroidal Alfven eigenmodes (TAE) were excited. The first direct measurements of the damping of TAE modes were carried out.

• OSTI ID: 165299
• Journal Information: Physics of Plasmas, Journal Name: Physics of Plasmas Journal Issue: 6 Vol. 2; ISSN PHPAEN; ISSN 1070-664X
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ALFVEN WAVES
DESIGN
DIVERTORS
HIGH-BETA PLASMA
ITER TOKAMAK
JET TOKAMAK
PLASMA CONFINEMENT
THERMONUCLEAR DEVICES
VACUUM PUMPS