Engineering Design of the National Spherical Tokamak Experiment

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

doi:dx.doi.org/10.13182/FST96-A11963134

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Engineering Design of the National Spherical Tokamak Experiment

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

Fusion Science and Technology / Volume 30 / Number 3P2B / December 1996 / Pages 1337-1341

Innovative Approaches to Fusion Energy / dx.doi.org/10.13182/FST96-A11963134

Published:February 9, 2018

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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.