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• W196569673 abstract "Advanced tokamak research on DIII-D is focused on developing a high fusion gain, steady-state scenario that would eliminate or greatly reduce the demands on an inductive transformer in future devices. Steady-state operation requires the inductively driven current density (jInd) be zero everywhere. Most of the total current Ip is from self-driven bootstrap current, with the remainder driven by external noninductive sources. This paper describes an extension of the fully noninductive condition (fNI~100%) to ~0.7 current relaxation times that was achieved by a combination of new scientific insights and more available ECCD. The insights are an optimization of performance through variation of the plasma shape parameter known as squareness (!) and an optimization of divertor magnetic balance. These optimizations simultaneously improve stability, confinement, and density control. These are each essential for achieving fully noninductive operation. Bootstrap current fraction fBS is proportional to normalized beta, ∀N = ∀T (%)/[Ip (MA)/a(m) BT (T)], where ∀T = 2µ0∀p# /B T 2 is the toroidal beta, a is the equivalent minor radius and BT the toroidal field. It is desirable to operate at the highest stable ∀N with the resulting jBS well aligned with jtotal. Density control is essential because as density increases, ECCD and neutra l beam current drive (NBCD) drive decrease faster than bootstrap current increases. Additional detai ls and relevant references are given in [1]. II. Squareness and Confinement" @default.
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• W196569673 date "2009-06-17" @default.
• W196569673 modified "2023-09-27" @default.
• W196569673 title "Plasma Shape Optimization for Steady-State Tokamak Development in DIII-D" @default.
• W196569673 hasPublicationYear "2009" @default.
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