Published December 1976 | Version v1
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Experimental results on the confinement and heating of the plasma in the TFR Tokamak

Description

TFR is a Tokamak device (R=98cm; a=20cm; Bsub(T)=60kG; Isub(p)=400kA). The best plasma characteristics obtained with ohmic heating are: Tsub(e)=2,5keV; Tsub(i)=1,2keV; tau=20msec; n tau=2.1012 cm2s-1. The electron power balance involves three regions in the plasma: the central region, inside the q=1 magnetic surface, which is dominated by MHD internal disruptions; the gradient region, between the q=1 and q=2 magnetic surfaces, which is dominated by a non classical heat conductivity, interpreted by the dissipative trapped electron drift mode; the outer shell in which radiate the light impurities, and where the conduction is non classical. The ion power balance is still inaccurate; the ionic heat transport coefficient is about twice the neoclassical value. A powerful neutral heating (600kW - D0 or H0 - 35keV) increases the ion temperature up to 2keV and the plasma enters into the so called collisionless regime. The heating is homogeneous through the plasma section, and the ion temperature increases linearly with the neutral injected power. The non growth in electron temperature is unexplained yet

Availability note (English)

MF available from INIS under the Report Number.

Abstract (French)

Le Tokamak TFR (R=98cm; a=20cm; Bsub(T)=60kG; Isub(p)=400kA) a permis d'atteindre en chauffage ohmique les performances maximales suivantes: Tsub(e)=2,5keV; Tsub(i)=1,2keV; tau=20msec: n tau=2.1012 cm2s-1. Le bilan de puissance electronique conduit a distinguer 3 zones dans le plasma: la zone centrale limitee par la surface magnetique ou q=1, qui est le siege de disruptions de type MHD; la zone intermediaire limitee par q=1 et q=2, qui est dominee par une forte conductivite thermique, interpretable par l'instabilite de derive en electrons pieges; la zone peripherique ou rayonnent les impuretes legeres, mais ou une part importante de la puissance est dissipee par une forte conduction. Le bilan de puissance ionique est encore imprecis, le coefficient de conduction thermique pour les ions est environ egal a 2 fois la valeur neoclassique. Un puissant chauffage (600kW) par injection de neutres (D0 ou H0 de 35keV) a permis d'atteindre 2keV pour les ions et d'entrer ainsi dans le regime non collisionnel. L'echauffement est homogene dans toute la section du plasma et croit proportionnellement a la puissance injectee. La non croissance de la temperature electronique n'est pas clairement expliquee

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Additional details

Additional titles

Original title (French)
Resultats experimentaux sur le confinement et le chauffage du plasma dans le Tokamak de Fontenay-aux-Roses (TFR)

Publishing Information

Imprint Pagination
41 p.
Report number
EUR-CEA-FC--870

Conference

Title
National congress on plasma physics.
Dates
6 Dec 1976.
Place
Paris, France.

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
8308220
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BEAM INJECTION HEATING; CONFINEMENT; ENERGY BALANCE; JOULE HEATING; NEUTRAL ATOM BEAM INJECTION; PLASMA DENSITY; TFR TOKAMAK
Descriptors DEC
BEAM INJECTION; CLOSED PLASMA DEVICES; HEATING; PLASMA HEATING; THERMONUCLEAR DEVICES; TOKAMAK DEVICES