NON-THERMAL DT YIELD WITH (D)T ICRH HEATING IN JET
Projections of the (D)T fusion yield expected during fundamental ICRH heating of D in JET tritium plasmas are presented. The highest fusion multiplication factor is achieved for a relatively high plasma density and minority concentration ratio about 20%-40% with dipole antenna. The latter reduces mode conversion and maximises the rf power coupled to the minority ions. Ray-tracing and global wave ICRH codes are used to calculate power deposition profiles; 80% is cyclotron damped by deuterium and 17% is coupled directly to electrons via TTMP and Landau damping. With launched rf power of 12MW deposited about 0.3m off-axis, fusion powers up to about 8MW are predicted for a range of JET plasmas with achieved plasma pressure 6 x 1.0 E20keV/m3 and Z(eff)=2. Projecting rf power to 25MW, fusion power increases to 17MW with Z(eff)=2.
Bibliographic Reference: REPORT: JET-P(89)34 EN (1989) AVAILABLE FROM THE PUBLICATIONS OFFICER, JET JOINT UNDERTAKING, ABINGDON, OXON. OX14 3EA (GB)
Record Number: 1989128047700 / Last updated on: 1990-11-09
Available languages: en