Review of recent experimental and modeling advances in the understanding of lower hybrid current drive in ITER-relevant regimes

JET Contributors

Research output: Contribution to journalReview articlepeer-review

24 Scopus citations

Abstract

Progress in understanding lower hybrid current drive (LHCD) at high density has been made through experiments and modeling, which is encouraging given the need for an efficient off-axis current profile control technique in burning plasma. By reducing the wall recycling of neutrals, the edge temperature is increased and the effect of parametric instability (PI) and collisional absorption (CA) is reduced, which is beneficial for increasing the current drive efficiency. Strong single pass absorption is preferred to prevent CA and high LH operating frequency is essential for wave propagation to the core region at high density, presumably to mitigate the effect of PI. The dimensionless parameter that characterizes LH wave accessibility and wave refraction for the experiments in this joint study is shown to bracket the region in parameter space where ITER LHCD experiments will operate in the steady state scenario phase. Further joint experiments and cross modeling are necessary to understand the LHCD physics in weak damping regimes which would increase confidence in predictions for ITER where the absorption is expected to be strong.

Original languageEnglish
Article number095003
JournalNuclear Fusion
Volume58
Issue number9
DOIs
StatePublished - 20 Jul 2018
Externally publishedYes

Bibliographical note

Publisher Copyright:
© EURATOM 2018.

Funding

This work is supported by the National Magnetic Confinement Fusion Science Program of China (Grant No. 2015GB102003, 2013GB106001B, 2013GB112003, 2015GB101002), the National Natural Science Foundation of China (Grant No. 11675214, 11175206, 11305211 and 11275233), the National Key R&D Program of China (Grant No. 2016YFA0400600, and 2016YFA0400602), Hefei Science Center CAS (2016HSC-IU008), the JSPS-NRF-NSFC A3 Foresight Program in the field of Plasma Physics (NSFC No. 11261140328), and K C Wong Education Foundation. Part of the work was conducted on the Alcator C-Mod tokamak, a DoE Office of Science user facility, and is supported by USDoE awards DE-FC02-99ER54512, DE-AC02-09CH11466, and DoE Grant DE-SC0010492. It is partly supported by the China-Italy and the China-France Collaboration program. We also give thanks to the support from the IOS TG of the ITPA. 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. Work has been part-funded by the RCUK Energy Programme (grant number EP/P012450/1).

FundersFunder number
China-France Collaboration program
DOE Office of Science
Hefei Science Center CAS2016HSC-IU008
IOS TG of the ITPA
JSPS-NRF-NSFC A3 Foresight Program in the field of Plasma Physics
K C Wong Education Foundation
National Key R&D Program of China2016YFA0400602, 2016YFA0400600
U.S. Department of EnergyDE-AC02-09CH11466, DE-FC02-99ER54512, DE-SC0010492
Horizon 2020 Framework Programme633053
H2020 Euratom
Research Councils UKEP/P012450/1
National Natural Science Foundation of China11175206, 11675214, 11305211, 11261140328, 11275233
National Magnetic Confinement Fusion Program of China2013GB106001B, 2013GB112003, 2015GB101002, 2015GB102003

    Keywords

    • ITER
    • lower hybrid current drive
    • magnetic fusion

    Fingerprint

    Dive into the research topics of 'Review of recent experimental and modeling advances in the understanding of lower hybrid current drive in ITER-relevant regimes'. Together they form a unique fingerprint.

    Cite this