EPJ Web Conf.
Volume 157, 201722 Topical Conference on Radio-Frequency Power in Plasmas
|Number of page(s)||5|
|Published online||23 October 2017|
The Role of Combined ICRF and NBI Heating in JET Hybrid Plasmas in Quest for High D-T Fusion Yield
1 Barcelona Supercomputing Center (BSC), Barcelona, Spain
2 ICREA, Pg. Lluís Companys 23, 08010 Barcelona, Spain
3 CCFE, Culham Science Centre, Abingdon, Oxon, OX14 3DB, UK
4 ENEA, Fusion and Nuclear Safety Dep., C.R. Frascati, Frascati (Roma), Italy
5 Ecole Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC), CH-1015 Lausanne, Switzerland
6 Max-Planck-Institut für Plasmaphysik, D-85748 Garching, Germany
7 Institute of Plasma Physics and Laser Microfusion, Hery 23, 01-497 Warsaw, Poland
8 Uppsala University, SE-75120 Uppsala, Sweden
9 CEA, IRFM, F-13108 Saint Paul Lez Durance, France
10 European Commission, B-1049 Brussels, Belgium
11 Laboratory for Plasma Physics, LPP-ERM/KMS, Renaissancelaan 30 Avenue de la Renaissance B-1000, Brussels Belgium
12 Institute of Physics, Opole University, ul. Oleska 48, Opole 45-052, Poland
13 Laboratorio Nacional de Fusión, CIEMAT, Madrid, Spain
14 ITER Organization, Route de Vinon, CS 90 046, 13067 Saint Paul Lez Durance, France
15 Consorzio RFX, corso Stati Uniti 4, 35127 Padova, Italy
* Corresponding author: firstname.lastname@example.org
Published online: 23 October 2017
Combined ICRF and NBI heating played a key role in achieving the world-record fusion yield in the first deuterium-tritium campaign at the JET tokamak in 1997. The current plans for JET include new experiments with deuterium-tritium (D-T) plasmas with more ITER-like conditions given the recently installed ITER-like wall (ILW). In the 2015-2016 campaigns, significant efforts have been devoted to the development of high-performance plasma scenarios compatible with ILW in preparation of the forthcoming D-T campaign. Good progress was made in both the inductive (baseline) and the hybrid scenario: a new record JET ILW fusion yield with a significantly extended duration of the high-performance phase was achieved. This paper reports on the progress with the hybrid scenario which is a candidate for ITER longpulse operation (∼1000 s) thanks to its improved normalized confinement, reduced plasma current and higher plasma beta with respect to the ITER reference baseline scenario. The combined NBI+ICRF power in the hybrid scenario was increased to 33 MW and the record fusion yield, averaged over 100 ms, to 2.9x1016 neutrons/s from the 2014 ILW fusion record of 2.3x1016 neutrons/s. Impurity control with ICRF waves was one of the key means for extending the duration of the high-performance phase. The main results are reviewed covering both key core and edge plasma issues.
© The authors, published by EDP Sciences, 2017
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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