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This paper describes a series of experiments in JET, culminating in the first tokamak discharges in deuterium-tritium fuelled mixtures. The objectives were: (i) to produce more than 1 MW fusion power in a controlled way; (ii) to validate transport codes and provide a basis for predicting accurately the performance of deuterium-tritium plasmas from measurements made in deuterium plasmas; (iii) to determine tritium retention in the torus systems and to establish the effectiveness of discharge cleaning techniques for tritium removal; (iv) to demonstrate the technology related to tritium usage; (v) to establish safe procedures for handling tritium in compliance with the regulatory requirements. A single-null X-point magnetic configuration, diverted onto the upper carbon target, with reversed toroidal magnetic field was chosen. Deuterium plasmas were heated by high power, long duration deuterium neutral beams from fourteen sources and fuelled also by up to two neutral beam sources injecting tritium. The results from three of these high performance hot ion H-mode discharges are described. The TRANSP code was used to check the internal consistency of measured data and to determine the origin of the measured neutron fluxes.

Additional information

Authors: JET TEAM, JET Joint Undertaking, Abingdon, Oxon. (GB)
Bibliographic Reference: Report: JET-P(91)66 EN (1991) 24 pp.
Availability: Available from the Publications Officer, JET Joint Undertaking, Abingdon, Oxon. OX14 3EA (GB)
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