ICRH physics and technology achievements in JET-ILW
EUROfusion Consortium, JET, Culham Science Centre, Abingdon, OX14 3DB, UK.
1 CCFE, Culham Science Centre, Abingdon, OX14 3DB, UK.
2 LPP-ERM/KMS, EUROfusion Consortium Member, TEC Partner, Brussels, Belgium.
3 Max-Planck-Institut fur Plasmaphysik, Boltzmannstr.2, D-85748, Germany.
4 CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France.
5 IPPLM, Hery 23 Str., 01-497 Warsaw, Poland.
6 Associazione ENEA, Fusion and Nuclear Safety Department, C. R. Frascati, Via E. Fermi 45, 00044 Frascati (Roma), Italy.
7 Centre de Recherches en Physique des Plasmas, EPFL, 1015 Lausanne, Switzerland.
8 Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, USA.
9 Barcelona Supercomputing Center (BSC), 08034 Barcelona, Spain.
10 ICREA, Pg. Lluis Companys 23, 08010 Barcelona, Spain.
11 Instituto de Plasmas e Fusão Nuclear, 1ST, Universidade de Lisboa, Portugal.
12 Department of Applied Physics, University Ghent, 9000 Gent, Belgium
* Corresponding author: firstname.lastname@example.org
Published online: 23 October 2017
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.
© The authors, published by EDP Sciences, 2017
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