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Abstract

The concept and the key features of the Joint European Torus (JET), flagship of the integrated European fusion research programme, departed considerably from those of other large tokamaks under design in the early 1970s. D-shape toroidal coils, vacuum vessel and plasma with large volumes and currents were unique and controversial features of JET. Moreover, since the early phase of the JET design, due consideration was given to D-T operations, including remote handling capability and D-T compatible peripheral systems. JET experimental results have confirmed the validity of these design choices. In turn, these choices had an impact on the development of other tokamaks and of Next Step design proposals, such as NET (Next European Torus) and later ITER (International Tokamak Experimental Reactor). Experimental evidence from JET and other tokamaks has clearly shown that the control of impurities is a key for finalising the ITER design. Therefore, the present JET programme is focused on a Divertor programme, with thermonuclear grade plasmas, tailored to ITER needs.

Additional information

Authors: BERTOLINI E, JET Joint Undertaking, Abingdon, Oxon. (GB);JET TEAM, JET Joint Undertaking, Abingdon, Oxon. (GB)
Bibliographic Reference: Report: JET-P(94)36 EN (1994) 17 pp.
Availability: Available from the Publications Officer, JET Joint Undertaking, Abingdon, Oxon. OX14 3EA (GB)
Record Number: 199510158 / Last updated on: 1995-08-22
Category: PUBLICATION
Original language: en
Available languages: en
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