The new phase of JET : The pumped divertorFunded under: FP2-FUSION 10C
The basic principle of the fusion process is the fusing of light nuclei to form heavier ones and the accompanying release of substantial energy. For a fusion reactor, there are several possible fusion reactions, but the one that is easiest to achieve is that between the deuterium and tritium isotopes of hydrogen. This D-T reaction is: D + T implies 4He + n + 17.6 MeV At the temperatures needed for this reaction to occur, the D-T fuel is in the plasma state, comprising a mixture of charged particles (nuclei and electrons), which can be contained by magnetic fields. The most effective magnetic configuration is the toroidal tokamak device, of which the Joint European Torus (JET) is the largest in operation. The aim of the new phase of the JET project is to demonstrate, prior to full D-T operation in JET, effective methods of impurity control in operating conditions close to those of a Next Step tokamak, with a stationary plasma of thermonuclear grade in an axisymmetric pumped divertor configuration. This new phase starting in 1992, and which is introduced in this report, should: (i) demonstrate a concept of impurity control; (ii) determine the size and geometry needed to realise this concept in a Next Step tokamak; (iii) allow a choice of suitable plasma facing components; (iv) demonstrate the operational domain for such a device.
Bibliographic Reference: Report: JET-P(92)17 EN (1992) 21 pp.
Availability: Available from the Publications Officer, JET Joint Undertaking, Abingdon, Oxon. OX14 3EA (GB)
Record Number: 199211049 / Last updated on: 1994-12-02
Original language: en
Available languages: en