ENERGY CONFINEMENT SCALING OF OHMIC AND ICRF HEATED JET PLASMAS
On attachment from GA Technologies Inc., USA, scaling studies of global energy confinement time have been carried out for various conditions on JET. Plasma density n, toroidal field B-T, safety factor q, major radius R and minor radius a have all been varied for ohmic plasmas. The global energy confinement time tau-E is found to scale as (nB-T)**1/2-q**1/3R**1.7a**1.3. In ICRF experiments, deuterium plasmas have been heated by 3He and H minority heating schemes. If the power radiated by the antenna is fully absorbed by the plasma, then the global energy confinement time tau-E deteriorates with rf heating power. The tau-E, however, improves with both plasma current I-p and toroidal field B-T, its scaling being approximately described by tau-E varies as P**1/2-/total I-p**1/2- B-T**1/2-, which is similar to the well known L mode scaling of neutrally heated plasmas, particularly in its power dependence. Comparisons with the L mode scaling of smaller tokamaks are made to determine the scaling of tau-E with plasma dimensions.
Bibliographic Reference: 27TH ANNUAL MEETING OF THE DIVISION OF PLASMA PHYSICS, SAN DIEGO (USA), NOV. 4-8, 1985 PAPER 6P53, PROCEEDINGS P.1525
Record Number: 1989124130100 / Last updated on: 1987-01-01
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