Progress toward commissioning and plasma operation in NSTX-U

被引：24

作者：

Ono, M. ^{[1
]}

Chrzanowski, J. ^{[1
]}

Dudek, L. ^{[1
]}

Gerhardt, S. ^{[1
]}

Heitzenroeder, P. ^{[1
]}

Kaita, R. ^{[1
]}

Menard, J. E. ^{[1
]}

Perry, E. ^{[1
]}

Stevenson, T. ^{[1
]}

Strykowsky, R. ^{[1
]}

Titus, P. ^{[1
]}

von Halle, A. ^{[1
]}

Williams, M. ^{[1
]}

Atnafu, N. D. ^{[1
]}

Blanchard, W. ^{[1
]}

Cropper, M. ^{[1
]}

Diallo, A. ^{[1
]}

Gates, D. A. ^{[1
]}

Ellis, R. ^{[1
]}

Erickson, K. ^{[1
]}

Hosea, J. ^{[1
]}

Hatcher, R. ^{[1
]}

Jurczynski, S. Z. ^{[1
]}

Kaye, S. ^{[1
]}

Labik, G. ^{[1
]}

Lawson, J. ^{[1
]}

LeBlanc, B. ^{[1
]}

Maingi, R. ^{[1
]}

Neumeyer, C. ^{[1
]}

Raman, R. ^{[2
]}

Raftopoulos, S. ^{[1
]}

Ramakrishnan, R. ^{[1
]}

Roquemore, A. L. ^{[1
]}

Sabbagh, S. A. ^{[3
]}

Sichta, P. ^{[1
]}

Schneider, H. ^{[1
]}

Smith, M. ^{[1
]}

Stratton, B. ^{[1
]}

Soukhanovskii, V. ^{[4
]}

Taylor, G. ^{[1
]}

Tresemer, K. ^{[1
]}

Zolfaghari, A. ^{[1
]}

机构：

[1] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA

[2] Univ Washington, Seattle, WA 98195 USA

[3] Columbia Univ, New York, NY 10027 USA

[4] Lawrence Livermore Natl Lab, Livermore, CA 94551 USA

来源：

NUCLEAR FUSION | 2015年 / 55卷 / 07期

关键词：

NSTX-U; spherical tokamak; FNSF;

D O I：

10.1088/0029-5515/55/7/073007

中图分类号：

O35 [流体力学]; O53 [等离子体物理学];

学科分类号：

070204 ; 080103 ; 080704 ;

摘要：

The National Spherical Torus Experiment-Upgrade (NSTX-U) is the most powerful spherical torus facility at PPPL, Princeton USA. The major mission of NSTX-U is to develop the physics basis for an ST-based Fusion Nuclear Science Facility (FNSF). The ST-based FNSF has the promise of achieving the high neutron fluence needed for reactor component testing with relatively modest tritium consumption. At the same time, the unique operating regimes of NSTX-U can contribute to several important issues in the physics of burning plasmas to optimize the performance of ITER. NSTX-U further aims to determine the attractiveness of the compact ST for addressing key research needs on the path toward a fusion demonstration power plant (DEMO). The upgrade will nearly double the toroidal magnetic field B-T to 1 T at a major radius of R-0 = 0.93 m, plasma current I-p to 2MA and neutral beam injection (NBI) heating power to 14MW. The anticipated plasma performance enhancement is a quadrupling of the plasma stored energy and near doubling of the plasma confinement time, which would result in a 5-10 fold increase in the fusion performance parameter n tau T. A much more tangential 2nd NBI system, with 2-3 times higher current drive efficiency compared to the 1st NBI system, is installed to attain the 100% non-inductive operation needed for a compact FNSF design. With higher fields and heating powers, the NSTX-U plasma collisionality will be reduced by a factor of 3-6 to help explore the favourable trend in transport towards the low collisionality FNSF regime. The NSTX-U first plasma is planned for the Summer of 2015, at which time the transition to plasma operations will occur.

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页数：11

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