THE JOINT EUROPEAN TORUS INSTALLATION - FIRST RESULTS AND PROSPECTS
In this report, information is provided on JET's machine design, parameters and operation on plasma diagnostics presently in operation, plasma optimization in the ohmic heating phase, impurity studies, confinement properties and scaling laws, and preliminary tests at ICRF frequencies. The results hitherto obtained, allow the following conclusions: JET behaves similarly to smaller Tokamaks (discharge and subsequent behaviour of the plasma); discharges up to 20s have been obtained without disruptions, even during current decay; plasma elongations of 1.2 to 1.6 (feedback controlled) and central electron temperatures (T-e up to 5 keV) and ion temperatures (T up to 3 keV) in ohmically heated plasmas (power input less than 3 MW, Zeff 3-10) have been achieved; energy confinement time (T-E) is better than extrapolation of INTOR scaling for a given plasma density; concerning the problem of impurity levels: later experiments with low-Z tiles on the inner walls and carbonized vessel showed reduced levels of metals and oxygen resulting in lower Zeff and decreased radiation losses. Lastly, initial experiments on ICRF heating showed that MW power levels may be coupled to the plasma. Future experiments will cluster around impurity control, uses of additional heating applied, and preparation for tritium operation.
Bibliographic Reference: WRITE TO THE PUBLICATIONS OFFICER, JET JOINT UNDERTAKING, ABINGDON, OXON, OX14 3EA (UK), MENTIONING REPORT JET-P(85)07, 1985
Record Number: 1989124115900 / Last updated on: 1987-01-01
Available languages: en