DIII-D research towards establishing the scientific basis for future fusion reactors
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Date
Authors
Petty, C. C.
Abadie, L.
Abrams, T. W.
Ahn, J.
Akiyama, T
Aleynikov, P.
Allcock, J.
Allen, E. O.
Allen, S. L.
Anderson, J. P.
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IOP Publishing
Abstract
DIII-D research is addressing critical challenges in preparation for ITER and the next
generation of fusion devices through focusing on plasma physics fundamentals that underpin
key fusion goals, understanding the interaction of disparate core and boundary plasma
physics, and developing integrated scenarios for achieving high performance fusion regimes.
Fundamental investigations into fusion energy science find that anomalous dissipation of
runaway electrons (RE) that arise following a disruption is likely due to interactions with
RE-driven kinetic instabilities, some of which have been directly observed, opening a new
avenue for RE energy dissipation using naturally excited waves. Dimensionless parameter
scaling of intrinsic rotation and gyrokinetic simulations give a predicted ITER rotation profile
with significant turbulence stabilization. Coherence imaging spectroscopy confirms near
sonic flow throughout the divertor towards the target, which may account for the convectiondominated parallel heat flux. Core-boundary integration studies show that the small angle slot
divertor achieves detachment at lower density and extends plasma cooling across the divertor
target plate, which is essential for controlling heat flux and erosion. The Super H-mode regime
has been extended to high plasma current (2.0 MA) and density to achieve very high pedestal
pressures (~30 kPa) and stored energy (3.2 MJ) with H98y2 ≈ 1.6–2.4. In scenario work, the
ITER baseline Q = 10 scenario with zero injected torque is found to have a fusion gain metric
βτE independent of current between q95 = 2.8–3.7, and a lower limit of pedestal rotation for
RMP ELM suppression has been found. In the wide pedestal QH-mode regime that exhibits
improved performance and no ELMs, the start-up counter torque has been eliminated so that
the entire discharge uses ≈0 injected torque and the operating space is more ITER-relevant.
Finally, the high-βN (⩽3.8) hybrid scenario has been extended to the high-density levels
necessary for radiating divertor operation, achieving ~40% divertor heat flux reduction using
either argon or neon with Ptot up to 15 MW.
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Nuclear Fusion
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Open Access
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Creative Commons Attribution 3.0 licence
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