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, Q (≡Pfus/Pr.f.), is achieved for a relatively high plasma density (ne0 > 5 x 1019 m-3) and minority concentration ratio nD/nT ≅ 20-40% with dipole antenna (k ||∼ 7 m-1). The latter reduces mode conversion and maximizes the r.f. power coupled to the minority ions. We have used ray-tracing and global wave ICRH codes 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 r.f. power Pr.f. = 12 MW deposited ∼ 0.3 m off-axis, we predict fusion powers Pfus up to ∼ 8 MW for a range of JET plasmas with achieved plasma pressure Ne0Te0 - 6 x 1020keV m-3 and Zeff = 2. Projecting to Pr.f. = 25 MW, Pfus increases to 17 MW with Zeff = 2. (author)