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Abstract

The key experimental results, in the Ohmic Heating conditions, exceeded expectations, allowing a fusion parameter of (n-iD T-E T-i) = 0.5 10**20m**- 3-s.k.eV to be reached. Preliminary experiments with ICRH heating have produced ion temperatures up to 4 keV using less than 20% (<or=5 MW) of the additional heating power which will be eventually available. However, further enhancements of the machine are necessary to enable JET to reach its ultimate goal: Modifications to the poloidal electromagnetic system to allow plasma currents up to 7MA, long pulses (>30s) at reduced currents, and to obtain a magnetic limiter configuration with two X-points up to 4MA; modification to the vessel to improve mechanical stability against vertical disruptions, to protect the walls facing the "X-points" and to allow density increase and control by pellet injection and pumping panels and/or pumped limiters; use of RF power to control sawteeth oscillations and plasma current profiles. At the same time, the existing programme of increasing additional heating power up to 25 MW or above, by neutral injection and ion cyclotron radio-frequency heating will continue. For active phase (D+T) operation, most of the remote handling tools are now available; the design, technical specification and prototype work for the tritium plant is proceeding.

Additional information

Authors: BERTOLINI E JET JOINT UNDERTAKING, ABINGDON (UK), JET JOINT UNDERTAKING, ABINGDON (UK)
Bibliographic Reference: 11TH SYMPOSIUM ON FUSION ENGINEERING, AUSTIN, TEXAS (USA), NOV. 18-22, 1985 PP. 1-1 - 1-11, WRITE TO THE PUBLICATIONS OFFICER, JET JOINT UNDERTAKING, ABINGDON, OXON OX14 3EA (UK), MENTIONING REPORT JET-P(85)26, 1985
Record Number: 1989125076400 / Last updated on: 1987-12-01
Category: PUBLICATION
Available languages: en
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