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Plasma ignition, magnetic fusion

In the Tokamak fusion reactor depicted in Fig. 21.9, electric current to the poloidal coils on the primary magnetic transformer generates the axial current in the secondary plasma composed of deuterium and tritium ions. These ions are heated to ignition temperature and then the reaction becomes self-sustaining. The toroidal field coil suspends the plasma away from the metal conducting walls. Contact with the wall would both cool the plasma below ignition temperature and contaminate the plasma with heavy ions. The relevant reactions are given below. [Pg.951]

There are in particular two linear versions of the Z-pinch for which Extrap could lead to schemes of fusion technological interest. First, the parameter ranges of stable operation of the pulsed high--density Z-pinch should become substantially extended in presence of Extrap conductors. Second, in a quasi Steady Z pinch stabilized by such conductors, the reduction of axial heat transport by the purely transverse magnetic field should make ignition possible in a pure plasma at technically realistic pinch lengths. ... [Pg.136]


See other pages where Plasma ignition, magnetic fusion is mentioned: [Pg.2794]    [Pg.151]    [Pg.151]    [Pg.16]    [Pg.874]    [Pg.124]    [Pg.51]    [Pg.26]    [Pg.953]    [Pg.234]    [Pg.815]    [Pg.399]    [Pg.419]    [Pg.273]    [Pg.378]    [Pg.1239]    [Pg.1240]   


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Fusion ignition

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