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1 edition of Steady-state current drive in tokamaks workshop summary. found in the catalog.

Steady-state current drive in tokamaks workshop summary.

Steady-state current drive in tokamaks workshop summary.

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Published by Dept. of Energy, Office of Fusion Energy, Division of Magnetic Confinement Systems, for sale by the National Technical Information Service in Washington, Springfield, Va .
Written in English

    Subjects:
  • Tokamaks.,
  • Fusion reactors.

  • Edition Notes

    SeriesDOE/ET -- 0077.
    ContributionsUnited States. Dept. of Energy. Division of Magnetic Confinement Systems.
    The Physical Object
    Paginationiv, 102 p. :
    Number of Pages102
    ID Numbers
    Open LibraryOL17538006M

    Colin Windsor studied at Oxford, gaining his DPhil in , and was a post-doctorial fellow at g Harwell he performed experiments on neutron scattering for many years before joining Culham Fusion Laboratory in He worked on neural net control of the COMPASS-D tokamak, on the spherical tokamak START and on the JET tritium campaign of @article{osti_, title = {Status of tokamak research}, author = {Rawls, J M}, abstractNote = {An overall review of the tokamak program is given with particular emphasis upon developments over the past five years in the theoretical and experimental elements of the program. A summary of the key operating parameters for the principal tokamaks throughout the world is given.

      A critical issue for sustaining high performance, negative central shear (NCS) discharges is the ability to maintain current distributions that are maximum off axis. Sustaining such hollow current profiles in steady state requires the use of non-inductively driven current sources. On the DIII-D experiment, a combination of neutral beam current drive (NBCD) and bootstrap current have been Author: T.A. Casper, L.L. Lodestro, L.D. Pearlstein, G.D. Porter, M. Murakami, L.L. Lao, Y.R. Lin-Lui, H.E.   In summary, a system code based on an established physics model has been developed and used to identify and quantify the main parameters that drive the performance of steady state tokamak pilot plants and reactors, and the main findings have been supported by analysis of the relevant tokamak physics equations.

    Steady-state, 1. st. stability tokamaks (monotonic q profiles) • Require minimization of current drive power • Operate at high aspect ratio (to reduce I), maximize bootstrap fraction (εβ. p ∼ 1) and raise on-axis q • Can achieve 60%% bootstrap fraction with β. N ∼ . T1 - Potential of neutral beam current drive for steady-state and quasi-steady-state tokamak reactors. AU - Okano, Kunihiko. AU - Yamamoto, Shin. AU - Sugihara, Masayoshi. AU - Fujisawa, Noboru. PY - /1/1. Y1 - /1/1Cited by: 6.


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Steady-state current drive in tokamaks workshop summary Download PDF EPUB FB2

Get this from a library. Steady-state current drive in tokamaks workshop summary. [United States. Department of Energy. Division of Magnetic Confinement Systems,]. stability, and multiple current drive systems for profile control.

Given this background, what are the opportunities for steady state tokamak research today. First, existing tokamaks can continue their efforts to sustain high performance modes in the correct parameter regimes for times as long as their magnet and current drive systems can operate. Three modes of current drive operation in a tokamak — continuous, cyclic, and rfinitiated-are studied for air core and iron core transformer.

It is found that the air core transformer is in general more flexible than the iron core transformer for current drive by: 4. SST-1 (steady state superconducting tokamak) is a plasma confinement experimental device in the Institute for Plasma Research (IPR), an autonomous research institute under Department of Atomic Energy, belongs to a new generation of tokamaks with the major objective being steady state operation of an advanced configuration ('D' Shaped) plasma.

It has been designed as a medium Type: Tokamak. Optimize Current Drive Techniques Enabling Steady-State Operation of Burning Plasma Tokamaks R.

Prater, R.I. Pinsker, V. Chan, A. Garofalo, C. Petty, M. Wade General Atomics EXECUTIVE SUMMARY The attractiveness of the Fusion Nuclear Science Facility (FNSF) and future steady-state. A tokamak (Russian: Токамáк) is a device which uses a powerful magnetic field to confine a hot plasma in the shape of a tokamak is one of several types of magnetic confinement devices being developed to produce controlled thermonuclear fusion ofit is the leading candidate for a practical fusion reactor.

Tokamaks were initially conceptualized in the s by. Steady state operation of fusion reactors avoids many of the cyclic loads and the associated fatigue of pulsed devices. Extensive experimental and the Cited by: 1. Development of a Steady State Fusion Core – The Advanced Tokamak Path R.

Buttery et al. 2 (iii) To determine the path to self-consistent fully non-inductive operation through high b P and b T plasmas with flexible current profiles, increased heating power and new current drive tools. The steady-state current drive system for the Vulcan tokamak concept has been designed, taking into account requirements of high field, small size, and high operational wall temperature (B 0 = 7 T, R 0 = m, T wall > K).This lower hybrid current drive system allows steady-state operation by utilizing high field side launch, high RF source frequency (8 GHz), and dedicated current drive Cited by: Stabilization of magnetic islands in tokamaks by localized heating and current drive: a numerical approach Citation for published version (APA): Lazzari, De, D.

Stabilization of magnetic islands in tokamaks by localized heating and current drive: a numerical : D Diego De Lazzari. SST Joining the ranks of superconducting research tokamaks. The Indian Steady State Superconducting Tokamak (SST-1) was fully commissioned in Located at the Institute for Plasma Research in Gujarat, India, SST-1 produces repeatable plasma discharges up to ~ ms with plasma currents in excess of A at a central field of T.

The resulting efficient current drive provides a robust, steady state core plasma far from disruptive limits. ARC uses an all-liquid blanket, consisting of low pressure, slowly flowing fluorine Author: Thomas James Dolan.

tokamak[′täkə‚mak] (plasma physics) A device for confining a plasma within a toroidal chamber, which produces plasma temperatures, densities, and confinement times greater than that of any other such device; confinement is effected by a very strong externally applied toroidal field, plus a weaker poloidal field produced by a toroidally directed.

Coster D.P. et al., Divertor Design: Issues Raised by Steady State and Advanced Tokamak Operation threshold but its high Z so that main plasma contamination might pose a problem.

DEVELOPMENT OF STEADY-STATE ADVANCED TOKAMAK RESEARCH IN THE DIII-D TOKAMAK T. LUCE* General Atomics, P.O. BoxSan Diego, California Received Aug Accepted for Publication Decem Research into the feasibility of steady-state opera-tion of high-fusion-gain tokamak plasmas is one of the.

Moreau D. et al., Plasma control in Advanced Steady state operation of Tokamaks inductively coupled plasma layers (cf. Fig. l).Of course, in our simulations, the current density profile is continuous and accurately calculated in ASTRA [7] by solving the resistive diffusion equation with well-de- fined non-inductive current sources.

We assumed that an. Fujita T. et al., RecentProgress Towards Steady State Tokamak Operation with Improved Confinement in JTU-2 3 I-0)r12). steady-state operation in RS mode with Heff= and Q= It is found that the position of the tansport barrier depends on the fusion power and it is somewhat insensitive to the external current drive.

In both ELMy H mode and RS mode, the local heating in the region of low diffusivity is found beneficial to improve the plasma performance. @article{osti_, title = {The Spheromak path to fusion energy}, author = {Hooper, E.B., Barnes, C.W., Bellan, P.M.,}, abstractNote = {The spheromak is a simple and robust magnetofluid configuration with several attractive reactor attributes including compact geometry, no material center post, high engineering {beta}, and sustained steady state operation through helicity injection.

Steady state with low recirculating power Off-axis current drive to supply missing current — Provided by high power microwaves in DIII – D Other benefits of negative central shear profile — Reduced transport, improved confinement — Improved stability to central unstable MHD modes Ballooning Tearing modes Sawteeth f BS = q 4 3 2 1 0.

The purpose of the HIT program is to study and develop helicity injection current drive for magnetic confinement []. A fusion reactor requires an efficient method of steady-state current drive.

Current drive methods involving neutral beams and radio frequency waves have efficiencies as low as % when scaled to a reactor [4,5].Its aim is to develop a steady state capable advanced superconducting tokamak to establish a scientific and technological basis for an attractive fusion reactor.

The major parameters of the tokamak are: major radius m, minor radius m, toroidal field T and plasma current 2 MA, with a strongly shaped plasma cross-section and double.New spherical tokamak replacing TRIAM-1M. Mission to study issues related to steady-state operation within the All-Japan ST Research Program.

In particular, to develop a fully non-inductive current drive scheme that is effective in ST plasmas with high beta and high dielectric constant; to.