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The JET neutral beam injection (NBI) system has proved to be an extremely effective and flexible heating method, capable of producing high performance plasmas and performing a wide range of related physics experiments. High fusion performance deuterium plasmas have been obtained in the hot ion (HI) H-mode regime, using the central particle fuelling and ion heating capabilities of the NBI system in low target density plasmas, and in the pellet enhanced plasma H-mode regime, where the good central confinement properties of pellet fuelled plasmas are exploited by additional heating and fuelling as well as the transition to H-mode. The HI H-mode configuration was used for the first tritium experiment in which NBI was used to heat the plasma using 14 D(0) beams and, for the first time, to inject T(0) using the two remaining beams. These plasmas had a peak fusion power of 1.7 MW from D-T fusion reactions. The capability for injection of a variety of beam species (H(0), D(0), 3He(0) and 4He(0)) has allowed the study of confinement variation with atomic mass and the simulation of alpha-particle transport. Additionally, the use of the NBI system has permitted an investigation of the plasma behaviour near the toroidal beta limit over a wide range of toroidal field strengths.

Additional information

Authors: THOMPSON E ET AL., JET Joint Undertaking, Abingdon, Oxon. (GB)
Bibliographic Reference: Report: JET-P(92)68 EN (1992) 43 pp.
Availability: Available from the Publications Officer, JET Joint Undertaking, Abingdon, Oxon. OX14 3EA (GB)
Record Number: 199310284 / Last updated on: 1994-11-29
Original language: en
Available languages: en