Lower hybrid heating and current drive system for a tokamak reactor

Ehst, D.A.; Boley, C. D.; Evans, K.; Jung, Jungchung; Trachsel, C.A.; Hino, Tomoaki

doi:10.1007/bf01052392

Cited by 19 publications

(15 citation statements)

References 28 publications

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“…To attain more centrally peaked current profiles, Yuen et al (1980) suggest lower density, higher magnetic field operation, so as to allow the lower-hybrid wave to be accessible to the plasma center. Ehst et al (1982) present an improved account of the Starfire approach, including a discussion of the physics issues regarding stability and integrating the rf system into the overall power plant design.…”

Section: Reactor Considerationsmentioning

confidence: 99%

Theory of current drive in plasmas

1987

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The continuous operation ot a tokamak fusion reactor requires, among other things, a means of providing continuous coroidal current. Such operation is preferred to the conventional pulsed operation, where the plasma current is induced by a time-varying magnetic field. A variety of methods has been proposed to provide continuous current, including methods which utilize particle beams or radio frequency waves in any of several frequency regimes. Currents as large as half a mega-amp have iiow been produced in the laboratory by such raeans, and experimentation in these techniques has now involved major tokamak facilities worldwide. DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of tbeir employees, makes any warranty, express or implied, or assumes any legal liability or responsi bility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents chat sis use would not infringe privately owned rights. Refer ence herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise docs not necessarily constituie or imply jls endorsement, recom mendation, or favoring by the United Stales Government or Bny agency thereof. The views and opinions or authors espresscd herein do not necessarily stale or reflect those of the United States Government nr imu .-n™. .1.-r United Statu Government or any agency thereof.

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Section: Reactor Considerationsmentioning

confidence: 99%

Theory of current drive in plasmas

1987

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“…For our purposes we concentrate on the sequence in Figure 1 labelled by a F -1.2. Each point in the sequence is scaled to a new equilibrium with g s 0.030 by an appropriate increase of q a [10]. The resulting set of equilibria, all with g = 0.030 but different q a values, is given in Table I.…”

Section: Equilibrium Options: Variation With Q Amentioning

confidence: 99%

Maximal bootstrap current tokamak equilibria in the first stability regime

Ehst¹,

Evans²

1989

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A series of tokamak equilibria are studied in order to identify characteristics which may maximize the proportion of toroidal current naturally provided by the bootstrap effect. These plasmas are typical of high field reactors considered by the ARIES [Advanced Reactor Innovation and Evaluation Study] collaboration and are assumed to have rather flat density profiles and broad pressure profiles. With the use of noninductive current drive to provide the seed current it is possible to operate with q aX jo " 2.0; this results in a (bootstrap-assisted) current drive power of P« n = 117 MW and a figure of merit y B = 1.12 for a reference reactor with T * 21 keV. For the reference reactor P f = 2880 MW so Q = 24. Without the bootstrap effect the absorbed current drive power would be P CD = 285 MW, so r = 1-[y/y) = 0.59.

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“…11 shows an upper limit to the coating thickness 6 Be if we restrict the substrate to 250"C, as proposed in Chap. 2: 6 fi < 18 ram at a surface heat load Wj^ = 0.75 MW/m 2 and 5 te < 7 • at W^ = 1.75 MW/m 2 .…”

mentioning

confidence: 94%

Tokamak burn cycle study: a data base for comparing long pulse and steady-state power reactors

Ehst¹,

Brooks²,

Cha³

et al. 1983

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High-speed current drive for various y^°^> required driver power, <°), net electric output, P n^» and magnetic field, B^ 2-6 2-5 Best theoretical low-speed current drive: y • 0.16 A/W with IoW' = Y (l) [l0 20 m" 3 x 7.0 m/10 kevl/[n o R 0 /f 1 '[1O 20 m" 3 x 7.0 m/10 kev]/[n e R 0 /T e J 2-8 2-6 Low-speed current drive for various yd) 2-8 2-7 Plasma current, required field, and Z e ff for power balance in 8-m reactor: P f = 3900 MW, W n = 3.5 MW/m 2 2-10 2-8 Ohmic reactor performance; higher BM increases magnet build, A TFC , decreasing the hole in the solenoid, RQJJ = R v , and reducing volt-seconds. Volt-seconds assume ABQJJ = 2 X 10 T; fusion period, tj, is based on (Spitzer) loop voltage, V» = 2.2 n a x IoZ eff [10 keV/Tj 3 / 2 2-10 2-9 Schematic OH burn cycle 2-11 2-10 Schematic IT burn cycle 2-11 2-11 Schematic CW burn cycle 2-14 3-1 Disruption damage for 100-ms thermal dump 3-3 3-2 Beryllium melting for various disruption times 3-4 3-3 Beryllium vaporization for various disruption times 3-4 3-4 Slab geometry for the front surface of a limiter 3-6 3-5 Cylindrical geometry at the leading edge of a limiter 3-7 LIST OF FIGURES (Contd.

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Lower hybrid heating and current drive system for a tokamak reactor

Cited by 19 publications

References 28 publications

Theory of current drive in plasmas

Theory of current drive in plasmas

Maximal bootstrap current tokamak equilibria in the first stability regime

Tokamak burn cycle study: a data base for comparing long pulse and steady-state power reactors

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