TY - JOUR
T1 - The Role of Combined ICRF and NBI Heating in JET Hybrid Plasmas in Quest for High D-T Fusion Yield
AU - Mantsinen, Mervi
AU - Challis, Clive
AU - Frigione, Domenico
AU - Graves, Jonathan
AU - Hobirk, Joerg
AU - Belonohy, Eva
AU - Czarnecka, Agata
AU - Eriksson, Jacob
AU - Gallart, Dani
AU - Goniche, Marc
AU - Hellesen, Carl
AU - Jacquet, Philippe
AU - Joffrin, Emmanuel
AU - King, Damian
AU - Krawczyk, Natalia
AU - Lennholm, Morten
AU - Lerche, Ernesto
AU - Pawelec, Ewa
AU - Sips, George
AU - Solano, Emilia R.
AU - Tsalas, Maximos
AU - Valisa, Marco
N1 - Publisher Copyright:
© 2017 The authors, published by EDP Sciences.
PY - 2017/10/23
Y1 - 2017/10/23
N2 - 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.
AB - 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.
UR - http://www.scopus.com/inward/record.url?scp=85032615708&partnerID=8YFLogxK
U2 - 10.1051/epjconf/201715703032
DO - 10.1051/epjconf/201715703032
M3 - Conference article
AN - SCOPUS:85032615708
SN - 2101-6275
VL - 157
JO - EPJ Web of Conferences
JF - EPJ Web of Conferences
M1 - 03032
T2 - 22nd Topical Conference on Radio-Frequency Power in Plasmas 2017
Y2 - 30 May 2017 through 2 June 2017
ER -