Abstract
ICRH was extensively used in the 2015-16 JET-ILW (ITER like wall) experimental campaign; bulk heating together with high-Z impurity chase-out from plasma centre importantly contributed to the good DD fusion performance obtained recently in JET. Power up to 6 MW was launched in H-mode deuterium plasmas and 8 MW during the hydrogen campaign. The ILA was re-installed and contributed positively to the availability of ICRH power. The ILA produces slightly less high-Z impurities than the A2's and the PWI measured via Be line emission on limiters is in the same ballpark. Specific experiments were conducted to optimise ICRH scenarios in preparation for DT in particular the dual frequency scheme, (H)D and (He)D were tested. In addition, it was confirmed that the (D)H scenario is accessible in a ILW environment and the novel 3-ions ICRH scheme was validated experimentally.
Highlights
In 2015 16, JET experiments were run to develop plasma scenarios in preparation for the DT campaign
ICRH was extensively used in the 2015 16 JET ILW (ITER like wall) experimental campaign; bulk heating together with high Z impurity chase out from plasma centre importantly contributed to the good DD fusion performance obtained recently in JET
The ILA produces slightly less high Z impurities than the A2’s and the Plasma Wall Interaction (PWI) measured via Be line emission on limiters is in the same ballpark
Summary
In 2015 16, JET experiments were run to develop plasma scenarios in preparation for the DT campaign. The paper describes the progress to reliably and efficiently deliver high ICRH power to the plasma and describes experiments aiming at optimizing ICRH heating scenarios in preparation for the JET DT campaign and ITER non active phase operation.
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