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Abstract

The status of knowledge of tokamak discharge with a bundle divertor is described, in particular concerning the effectiveness of a bundle divertor for compositional control and exhaust, first for tokamak experiments, then for the Next European Torus (NET). The bundle divertor is predicted to have considerable potential to exhaust helium and power and to control impurities, but only at values of the safety factor, q-s >= 3, which correspond to good confinement discharge. Fuelling via a bundle divertor appears to offer the realistic advantages for NET of using a local divertor or pair of divertor as the sole tritium handling devices. If a bundle divertor is to be considered for NET it will be necessary to achieve (a) reactor, (b) flux limited electron energy transport into the divertor, with high recycling in the divertor, and (c) impurity control at low Mach numbers. These items will require experimental demonstration, using a new bundle divertor with low toroidal ripple and high field expansion. It will also be necessary to optimize the space required for the bundle divertor in a reactor, including access for maintenance.

Additional information

Authors: HARBOUR P J, CULHAM LABORATORY, ABINGDON (UK);JOHNSON P C CULHAM LABORATORY, ABINGDON (UK), CULHAM LABORATORY, ABINGDON (UK)
Bibliographic Reference: WRITE TO HER MAJESTY'S STATIONERY OFFICE, P.O. BOX 276, LONDON, SE1 9NH (UK), MENTIONING REPORT CLM-R258, 1985, PRICE: UKL 7.00
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