Page 299 - Fundamentals of Magnetic Thermonuclear Reactor Design
P. 299

278     Fundamentals of Magnetic Thermonuclear Reactor Design


            condition and the initial approximation effect. In our case, the convergence is
            achieved if filaments inside the plasma instead of those nearby the magnetic
            field sensors are referred to as an initial approximation.
               The method of movable current filaments is universal with respect to type of
            sensors and their locations.
               The fixed current filament method is also based on a model of thin current
            filaments. The filament coordinates are specified, and the current amplitudes
 y¯         are derived by the best agreement between the calculated (y ) and measured (y)
                                                            j
            components of the poloidal magnetic field or measured flux in places where
 rj,zj;j=1,...,M  sensors and loops are located (rz j,; j  = 1,...,  M). This condition is identical to
                                      j
            the minimum of functional
                                         M  y ( − y ) 2
 2
 J=∑i=1Myi−y¯i σi2,                  J = ∑  i σ 2  i  ,                (8.71)
                                         =
                                        i 1   i
                                                       th
            where M is the number of measurements, and σ  is the i  measurement’s standard
                                                 i
            deviation. The optimum locations and number of current filaments are selected
            by the fixed current filament method, provided that the deviation of the recon-
            structed boundary by the current filaments from some basic boundary with a
            known shape is minimal.
               A comprehensive comparison of these methods suggests that the technique
            best fitted to the plasma control at every stage of the discharge is the movable
            current filament method.

            REFERENCES
              [1]  A. Portone, Perturbed solutions of fixed boundary MHD equilibria, Nucl Fusion 44 (2004)
                265.
              [2]  V. Belyakov, A. Kavin, Derivation of the linear models for the analysis of the plasma current,
                position and shape control system in tokamak devices, in: Proceedings of the International
                Conference ‘Physics and Control’ St. Petersburg, Russia, 2003.  pp. 1019–1024.
              [3]  R.R. Khayrutdinov, V.E. Lukash, Studies of plasma equilibrium and transport in a tokamak
                fusion device with the inverse-variable technique, J. Comp. Phys. 107 (2) (1993) 106.
              [4]  V. Lukash, Y. Gribov, A. Kavin, R. Khayrutdinov, M. Cavinato, Simulations of ITER sce-
                narios, Plasma Devices Oper. 13 (2) (2005) 143–156 (June).
              [5]  D.A. Ovsyannikov, E.I.  Veremey,  A.P. Zhabko,  V.A. Belyakov,  A.A. Kavin, in: Proc. of
                3rd International Workshop ‘Beam Dynamics & Optimization’ (BDO-96), St. Petersburg,
                  Russia,1996 1–5 July.  pp. 218–229.
              [6]  J.C. Doyle, B.A. Francis, A.R. Tannenbaum, Feedback Control Theory, MacMillan Publ. Co,
                New York; Toronto,  (1992) pp. 1–227.
              [7]  B. Lloyd, P.G. Carolan, C.D. Warrick, ECRH-assisted start-up in ITER, Plasma Phys. Con-
                trolled Fusion 38 (1996) 1627.
              [8]  V.A. Belyakov,  A.A. Kavin, S.A. Lepikhov,  A.B. Mineev,  A.D. Ovsyannikov,
                                          (Tokamak: The Initial Stage of a Discharge), Lan’
                Publishing House, Saint Petersburg, Russia,  (2014) pp. 1–176. (www.e.lanbook.com).
   294   295   296   297   298   299   300   301   302   303   304