TITLE

Structure of Global Tokamak Scalings

AUTHOR(S)
Dnestrovskij, Yu. N.
PUB. DATE
February 2002
SOURCE
Plasma Physics Reports;Feb2002, Vol. 28 Issue 2, p166
SOURCE TYPE
Academic Journal
DOC. TYPE
Article
ABSTRACT
In empirical tokamak scalings, not all of the standard engineering parameters are independent. Thus, the larger the tokamak, the higher the required plasma current and input power. Also, by using higher magnetic fields, it is possible to raise the plasma density. Instead of the plasma density, plasma current, and input power, it is proposed to use such combinations of engineering parameters whose values are essentially the same for different tokamaks. With this approach, the number of free scaling parameters can be reduced from six to three, thereby improving the reliability of the scaling. © 2002 MAIK “Nauka / Interperiodica”.
ACCESSION #
7293668

 

Related Articles

  • High-Q plasmas in the TFTR tokamak. Jassby, D. L.; Barnes, C. W.; Bell, M. G.; Bitter, M.; Boivin, R.; Bretz, N. L.; Budny, R. V.; Bush, C. E.; Dylla, H. F.; Efthimion, P. C.; Fredrickson, E. D.; Hawryluk, R. J.; Hill, K. W.; Hosea, J.; Hsuan, H.; Janos, A. C.; Jobes, F. C.; Johnson, D. W.; Johnson, L. C. // Physics of Fluids B: Plasma Physics;Aug91, Vol. 3 Issue 8, p2308 

    In the Tokamak Fusion Test Reactor (TFTR) [Plasma Phys. Controlled Fusion 26, 11 (1984) ], the highest neutron source strength S[sub n] and D-D fusion power gain Q[sub DD] are realized in the neutral-beam-fueled and heated "supershot" regime that occurs after extensive wall conditioning to...

  • Sawtooth studies with q-profile measurement on TFTR(abstract)[sup a]. Levinton, F.M.; Batha, S.H.; Yamada, M.; Zakharov, L.; Zarntorff, M.C. // Review of Scientific Instruments;Jan1995, Vol. 66 Issue 1, p372 

    Measures the q profile for plasma equilibrium and theories of MHD instabilities in a Tokamak Fusion Test Reactor (TFTR). Measurement of diagnostic and accurate profiles.

  • Performance of the Tokamak Fusion Test Reactor bolometers. Schivell, J. // Review of Scientific Instruments;May85, Vol. 56 Issue 5, p972 

    For the past year we have been making use of a horizontally viewing 19-channel array and a bolometer which views a narrow cross-sectional slice of the plasma. More recently, we have also obtained results from a second, vertically viewing array. Software has been developed to translate the data...

  • Experimental Studies of the Behavior of the Ion Plasma Component during Disruptive Instability in a Tokamak. Brevnov, N. N.; Gott, Yu. V.; Shurygin, V. A. // Plasma Physics Reports; 

    Results are presented from experimental studies of the behavior of the plasma ion component during disruptive instability in the TVD and DAMAVAND tokamaks. It is shown that the ion temperature increases during a major disruption by a factor of 1.5–2. The ions are accelerated predominantly...

  • Development of laser methods for diagnosing the surface state of the walls of the discharge chambers in tokamak facilities. Mukhin, E.; Kuteev, B.; Razdobarin, G.; Tolstyakov, S. // Instruments & Experimental Techniques;Mar2006, Vol. 49 Issue 2, p280 

    A method for diagnosing plasma-induced coating deposited on the walls of the discharge chambers in tokamak facilities is described. This method is based on the atomization of the laser-ablated thin layer of the material deposited on the wall and the determination of the amount of the evaporated...

  • Acceleration of neon pellets to high speeds for fusion applications. Combs, S.K.; Love, T.L.; Jernigan, T.C.; Milora, S.L.; Frattolillo, A.; Migliori, S. // Review of Scientific Instruments;Mar96, Vol. 67 Issue 3, p837 

    Proposes a technique for the injection of impurity pellets into the plasmas of tokamak fusion reactors. Aim to lessen the deleterious effects of plasma disruptions; Acceleration time of neon pellets; Change from deuterium to neon operation.

  • Real-time electron density measurements from Cotton–Mouton effect in JET machine. Brombin, M.; Boboc, A.; Zabeo, L.; Murari, A.; JET-EFDA Contributors // Review of Scientific Instruments;Oct2008, Vol. 79 Issue 10, p10E718 

    Real-time density profile measurements are essential for advanced fusion tokamak operation and interferometry is a proven method for this task. Nevertheless, as a consequence of edge localized modes, pellet injections, fast density increases, or disruptions, the interferometer is subject to...

  • Measurements of DT and DD neutron yields by neutron activation on the Tokamak Fusion Test Reactor. Barnes, Cris W.; Larson, Alvin R.; LeMunyan, G.; Loughlin, M.J. // Review of Scientific Instruments;Jan1995, Vol. 66 Issue 1, p888 

    Activates a variety of elemental foils by neutron fluence from the Tokamak Fusion Test Reactor (TFTR) under conditions with the deuterium-tritium (D-T) plasma neutron yield. Linear response over the large dynamic range obtained by reducing the mass of the foils; Increase of cooling time while...

  • Quasi-Stability of a Plasma Bicylinder. Vlasov, V. P.; Trubnikov, B. A. // Technical Physics;Jul2003, Vol. 48 Issue 7, p858 

    Observations seem to indicate that, in the plasmas of tokamaks and Z-pinches, short-lived closed current loops (filaments) can arise, each of which is composed of a pair of countercurrents flowing within the two halves of the cross section of the plasma cylinder in directions perpendicular to...

Share

Read the Article

Courtesy of THE LIBRARY OF VIRGINIA

Sorry, but this item is not currently available from your library.

Try another library?
Sign out of this library

Other Topics