Optimization of the N∥ Upshift in the DIII-D high field side lower hybrid current drive experiment

Rutherford, Grant; Frank, Samuel J.; Seltzman, Andrew H.; Bonoli, Paul T.; Wukitch, Stephen J.

doi:10.1088/1361-6587/ad44d6

Title: Optimization of the N_∥ Upshift in the DIII-D high field side lower hybrid current drive experiment

Journal Article · 08 May 2024 · Plasma Physics and Controlled Fusion

DOI: https://doi.org/10.1088/1361-6587/ad44d6 · OSTI ID:2406266

^[1];

^[2];

^[2]; Bonoli, Paul T. ^[2]; Wukitch, Stephen J. ^[2]

Massachusetts Institute of Technology (MIT), Cambridge, MA (United States); General Atomics
Massachusetts Institute of Technology (MIT), Cambridge, MA (United States)

High field side lower hybrid current drive (LHCD) is one potential candidate for efficient non-inductive current drive in tokamak power plants, and the first test of this technology will occur on the DIII-D tokamak during the 2024 campaign. Previous LFS launch experiments operated in the multi-pass regime and relied on scrape-off layer interactions to close the spectral gap. In the DIII-D experiment, single-pass damping is achievable via an upshift in the parallel refractive index N_∥ caused by mode converting twice (slow → fast → slow). This mode conversion affects the ray trajectories and can lead to enhanced N_∥ upshift depending on where mode conversion occurs. Compared to multi-pass absorption experiments, the optimization of launched N_∥ and plasma parameters can be counter-intuitive: increased density may increase efficiency and smaller N_∥,launch tend to damp closer to the separatrix. A hard x-ray camera installed to measure the bremsstrahlung (50–250 keV) radiation from LHCD-generated fast electrons is capable of verifying the trends reporting in this paper through comparison to the ray-tracing/Fokker–Planck codes GENRAY/CQL3D.

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Research Organization:: General Atomics, San Diego, CA (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: FC02-01ER54648; FC02-04ER54698; SC0014264

OSTI ID:: 2406266

Journal Information:: Plasma Physics and Controlled Fusion, Journal Name: Plasma Physics and Controlled Fusion Journal Issue: 6 Vol. 66; ISSN 0741-3335

Publisher:: IOP ScienceCopyright Statement

Country of Publication:: United States

Language:: English

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70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DIII-D tokamak
high field side launch
lower hybrid current drive
mode conversion

Title: Optimization of the N∥ Upshift in the DIII-D high field side lower hybrid current drive experiment

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Title: Optimization of the N_∥ Upshift in the DIII-D high field side lower hybrid current drive experiment