Page 22 - Fundamentals of Magnetic Thermonuclear Reactor Design
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4     Fundamentals of Magnetic Thermonuclear Reactor Design


               A discharge current and a toroidal magnetic field relate as

                                             a
                                      2 π B t0    2
 2
 Ip≤2πBt0q⋅µ ⋅aR ⋅R               I p  ≤  µ ⋅ q  0  ⋅  ⋅ R            (1.5)
                                             
 0
                                             R
 µ 0        where µ  is magnetic permeability.
                   0
               One of the tokamak’s important characteristics is the ratio between plasma
            gas-kinetic pressure and the pressure of a confining magnetic field.
                                        k  ⋅⋅ (T  + T  ) i
                                           n
                                    β =  B  2  e                        (1.6)
                                     t
 βt=kB⋅n⋅Te+TiBt02/2µ 0                   B /2 µ 0
                                           t0
            where k  is the Boltzmann constant. In a magnetohydrodynamic approximation,
                  B
                                           a
 βt≤aR⋅q2.                            β ≤     ⋅                         (1.7)
                                       t
                                          Rq ⋅  2
               For a tokamak with an aspect ratio (R/а) of around 3.3, β  is close to 3% if
                                                             t
            the stability criterion q is set at around 3. Apparently, the magnetic field pressure
            must be essentially greater than the plasma gas-kinetic pressure. In other words,
            it is the magnetic field’s ‘brutal force’ that confines plasma within a tokamak.
               One may increase the β  parameter a little extending the plasma column’s
                                   t
            cross-section along the vertical axis and let it obtain a D shape. This will allow
                               2
            an approximately (1+ k )/2 times increase in the stability margin and maximum
            allowable plasma current.
               Spherical tokamaks, notable for their aspect ratio close to 1, can increase the
            β . For example, a β  of around 40% was achieved in some experiments on the
                            t
             t
            NSTX spheromak (having an aspect ratio of 1.3).
               From these estimates and the expression (1.1), we derive the power of a
            fusion device based on the tokamak concept:
                                         < σv >
                                     2
                                                   ⋅
 2                            p  = k β B 4  ⋅  ⋅EV                      (1.8)
 pfus=kβt2Bt04⋅〈σv〉kBT ⋅Ef⋅Vp⋅  fus  t  t 0   ) 2  f  p
                                         (kT
                                           B
               Modern electromagnetic systems, including superconducting ones, can gen-
            erate fields up to (5–6) T at the plasma column axis (12–13 T ‘on the winding’).
            Considering this limitation and using the expression (1.8), one can derive an
            approximate volume density of heat generated by a tokamak; it is close to
                   3
            1 MW/m .
               In conclusion, we note that the tokamak, unlike its fission counterpart, can-
            not be small and low-power in principle. As follows explicitly from (1.3) and
            (1.8), it must be a large device with a heating power of around 1 GW. A range of
            problems in areas, such as magnetic, vacuum and cryogenic technologies; radia-
            tion materials science; thermal engineering; radiochemistry; electronics; pulse
            electrical engineering and automated control systems, must be solved on the
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