Modelling one-third field operation in the ITER pre-fusion power operation phase

M. Schneider,A. R. Polevoi,S. H. Kim,A. Loarte,S. D. Pinches,J-F Artaud, E. Militello-Asp, B. Beaumont, R. Bilato, D. Boilson,D. J. Campbell, P. Dumortier,D. Farina,L. Figini, Y. Gribov,M. Henderson,R. R. Khayrutdinov,A. A. Kavin, F. Kochl, T. Kurki-Suonio, A. Kuyanov, P. Lamalle,E. Lerche,V. E. Lukash, A. Messiaen,V Parail,K. Sarkimaki,A. Snicker,D. Van Eester

NUCLEAR FUSION(2019)

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摘要
In the four-stage approach of the new ITER Research Plan, the first pre-fusion power operation (PFPO) phase will only have limited power available from external heating and current drive (H&CD) systems: 20-30 MW provided by the electron cyclotron resonance heating (ECRH) system. Accessing the H-mode confinement regime at such low auxiliary power requires operating at low magnetic field, plasma current and density, i.e. 1.8 T and 5 MA for a density between 40% and 50% of the Greenwald density. II-mode plasmas at 5 MA/1.8 T will also be investigated in the second PFPO phase when ITER will have its full complement of H&CD capabilities installed, i.e. 20-30 MW of ECRH, 20 MW of ion cyclotron resonance heating and 33 MW of neutral beam injection. This paper describes the operational constraints and the II&CD capabilities for such scenarios in hydrogen and helium plasmas, to assess their viability and the issues it will be possible to address with them. The modelling results show that 5 MA/1.8 T scenarios are viable and will allow the exploration of the H-mode physics and control issues foreseen in the ITER Research Programme in the PFPO phases.
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关键词
heating and current drive,ITER,one-third field operation,NBI,ICRH,ECRH,tokamak
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