Modelling of JET hybrid plasmas with emphasis on performance of combined ICRF and NBI heating

JET Contributors

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Abstract

During the 2015-2016 JET campaigns, many efforts have been devoted to the exploration of high-performance plasma scenarios envisaged for DT operation in JET. In this paper, we review various key recent hybrid discharges and model the combined ICRF+NBI heating. These deuterium discharges with deuterium beams had the ICRF antenna frequency tuned to match the cyclotron frequency of minority H at the centre of the tokamak coinciding with the second harmonic cyclotron resonance of D. The modelling takes into account the synergy between ICRF and NBI heating through the second harmonic cyclotron resonance of D beam ions, allowing us to assess its impact on the neutron rate R NT. For discharges carried out with a fixed ICRF antenna frequency and changing toroidal magnetic field to vary the resonance position, we evaluate the influence of the resonance position on the heating performance and central impurity control. The H concentration is varied between discharges in order to test its role in the heating performance. It is found that discharges with a resonance beyond ∼0.15 m from the magnetic axis R 0 suffer from MHD activity and impurity accumulation in these plasma conditions. According to our modelling, the ICRF enhancement of R NT increases with the ICRF power absorbed by deuterons as the H concentration decreases. We find that in the recent hybrid discharges, this ICRF enhancement varies due to a variation of H concentration and is in the range of 10%-25%. The modelling of a recent record high-performance hybrid discharge shows that ICRF fusion yield enhancement of ∼30% and ∼15% respectively can be achieved in the ramp-up phase and during the main heating phase. We extrapolate the results to DT and find that the best performing hybrid discharges correspond to an equivalent fusion power of ∼7.0 MW in DT. Finally, an optimization analysis of the bulk ion heating for the DT scenario reveals around 15%-20% larger bulk ion heating for the 3He minority scenario as compared to the H minority scenario.

Original languageEnglish
Article number106037
JournalNuclear Fusion
Volume58
Issue number10
DOIs
StatePublished - Sep 5 2018

Funding

One of the authors (D. Gallart) would like to thank Dr. J.C. Wright and Dr. H. Weisen for carefully reading the present work and for their useful comments. D. Gallart would also like to thank Dr. P. Buratti for providing MHD related data. This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. D. Gallart is grateful to ‘la Caixa’ for supporting his PhD studies. This work has received funding from the Spanish Ministry of Economy and Competitiveness (MINECO) under grant ENE2015-67371-R.

FundersFunder number
Euratom research and training programme 2014–2018
Spanish Ministry of Economy and Competitiveness
Horizon 2020 Framework Programme633053
Horizon 2020 Framework Programme
Ministerio de Economía y CompetitividadENE2015-67371-R
Ministerio de Economía y Competitividad

    Keywords

    • ICRF heating
    • JET hybrid plasmas
    • NBI heating
    • fusion enhancement

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