1 - Nuclear Sciences and Applications - IAEA

240 AZIZOV et al.
TABLE I. TSP PARAMETERS AND EXPECTED PLASMA PARAMETERS
Parameters
Plasma volume (m 3 )
Major radius of column (m)
Minor radius of column (m)
Toroidal field on column axis (T)
Current in plasma at Ip = 2 (MA)
Duration of toroidal field area (s)
Compression time (s)
Additional heating power
(injection + HF) (MW)
Mean plasma density (m~ 3 )
Mean ion temperature (keV)
Mean electron temperature (keV)
Energy confinement time (ms)
Thermonuclear power (MW)
Before
compression
2.14
1.06
0.32
2.0
0.48
0.2
-
1 + 1
5 x 10"
0.5/1.2"
0.6/1.1*
0.175/0.6
30-50
First figure "before heating", second figure "after heating".
—
After
compression
of type "a"
0.856
1.06
0.2
5.0
0.48
0.2
0.01
1.3 x 10 20
2.0
1.9
1.0
125
—
After
compression
of type "b"
0.13
0.415
0.128
12.8
1.23
—
0.01
8 x 10 20
Ri = 41.5 cm for 10 ms. In this case, the toroidal field at radius R, after compression
attains 12.8 T. The tokamak parameters and expected plasma parameters are
given in Table I, and the cross-section of the toroidal field winding is shown in
Fig. 1. They were chosen on the basis of the possibilities of pulsed energetics and
in order to obtain a plasma with thermonuclear parameters, in which the released
thermonuclear power would be comparable to the energy loss power (Q ~ 1).
In developing this design, the main emphasis was placed on the creation of a
powerful infrastructure — power supply system, shielded experimental hall, control
system, tritium system — of relative simplicity and cheapness of the tokamak device
itself, permitting fast replacement by a new system according to the progress of
physical ideas and the growth of the technical possibilities.
Along the path chosen the whole complex of difficult technical problems resulting
from the necessity to generate a strong fast varying field in a great volume should
be solved. In doing so, a number of new, non-standard technical solutions have been
adopted [4].
7.0
6.0
1.3
10
3.5