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The properties of the ignition domain of a tokamak fusion reactor and the plasma thermal stability are analysed with a zero-dimensional model, both in steady state and with time dependent terms. Transport losses are modelled according to several confinement scalings. For a given device, ignition curves vary substantially according to the scaling laws used. If the global confinement time is calculated by combining ohmic and auxiliary heating scalings, a minimum density for ignition is generated. The general feature is the existence of two limiting temperatures. Analysis of the ignition domain shows that it is thermally unstable up to the upper temperature limit, with a characteristic time that is a function of the energy confinement time. It is found possible to stabilise the output power in the marginal ignition region with a fast feedback based on plasma density, together with plasma current, which can produce a wide range of output power at the maximum value of the total beta.

Additional information

Authors: APRUZZESE G, JET Joint Undertaking, Abingdon, Oxon. (GB);TANGA A, JET Joint Undertaking, Abingdon, Oxon. (GB)
Bibliographic Reference: Report: JET-P(88)65 EN (1988)
Availability: Available from the Publications Officer, JET Joint Undertaking, Abingdon, Oxon. OX14 3EA (GB)
Record Number: 198910740 / Last updated on: 1994-12-01
Original language: en
Available languages: en