Non-thermal DT yield with (D)T ICRH heating in JET

Abstract

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( identical to Pfus/PRF), is achieved for a relatively high plasma density (ne0>5*1019 m-3) and minority concentration ratio nD/nT approximately=20-40% with dipole antenna (k/sub /// approximately=7 m-1). The latter reduces mode conversion and maximizes the RF power coupled to the minority ions. The authors 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 RF power PRF=12 MW deposited approximately=0.3 m off-axis, the authors predict fusion powers Pfus up to approximately=8 MW for a range of JET plasmas with achieved plasma pressure ne0Te0=6*1020 keV m-3 and Zeff=2. Projecting to PRF=25 MW, Pfus increases in 17 MW with Zeff=2.