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Engineering Design of the National Spherical Tokamak Experiment

J. Spitzer, M. Ono, Y.K.M. Peng, D. Bashore, T. S. Bigelow, A. Brooks, J. Chrzanowski, Hanwen Fan, P. Heitzenroeder, T. R. Jarboe, R. Kaita, S. Kaye, H. Kugel, R. Majeski, C. Neumeyer, R. Parsells, E. Perry, N. Pomphrey, J. Robinson, D.J. Strickler, R. Wilson

Open publisher page 29 citations

Abstract

The National Spherical Tokamak Experiment (NSTX) is an ultra low aspect ratio device with a plasma current of 1 MA. The tokamak features auxiliary heating and current drive with a close-fitting conducting shell to maximize the plasma pressure. NSTX is designed for an experimental pulse length that will demonstrate quasi-steady state non-inductively driven advanced tokamak operation. The design also takes maximum advantage of existing facilities and components from previous Princeton devices to reduce the overall program costs.

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What this paper is about

The National Spherical Tokamak Experiment (NSTX) is an ultra low aspect ratio device with a plasma current of 1 MA. The tokamak features auxiliary heating and current drive with a close-fitting conducting shell to maximize the plasma pressure. NSTX is designed for an experimental pulse length that will demonstrate quasi-steady state non-inductively driven advanced tokamak operation. The design also takes maximum advantage of existing facilities and components from previous Princeton devices to reduce the overall program costs.

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OpenAlex reports 29 citations for this work. Citation counts describe recorded attention and do not establish research quality.

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Available abstract

The National Spherical Tokamak Experiment (NSTX) is an ultra low aspect ratio device with a plasma current of 1 MA. The tokamak features auxiliary heating and current drive with a close-fitting conducting shell to maximize the plasma pressure. NSTX is designed for an experimental pulse length that will demonstrate quasi-steady state non-inductively driven advanced tokamak operation. The design also takes maximum advantage of existing facilities and components from previous Princeton devices to reduce the overall program costs.

Key concepts: Tokamak, Spherical tokamak, Nuclear engineering, Current (fluid), Plasma, Steady state (chemistry), Materials science, Bootstrap current

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