The JET plasma boundary with limiter and X-point discharges
The JET tokamak has been operated in various limiter and magnetic separatrix configurations with ohmic, neutral beam and ion cyclotron heating. Radial profiles of plasma density, temperature and particle flux in the scrape-off layer have been measured and scalings with core plasma parameters have been established for the limiter discharges. In the magnetic separatrix configuration, H modes with energy confinement times up to 1s have been obtained with neutral beam heating. There are large, localised fluctuations in the edge parameters which appear to be well correlated with the periodic global particle losses. The main impurities are oxygen and carbon. The only significant metallic impurity is nickel which originates from the ion cyclotron heating antennas.
Bibliographic Reference: Report: JET-P(88)34 EN (1988)
Availability: Available from the Publications Officer, JET Joint Undertaking, Abingdon, Oxon. OX14 3EA (GB)
Record Number: 198910252 / Last updated on: 1994-12-01
Original language: en
Available languages: en