[en] The technique of transient electromagnetic processes analysis in azimuthal-sectional constructions, using the coupled circuit approach, is considered. Calculational results of a vertical magnetic field and a vortex electromotive force (e.m.f.) penetration through the blanket of a tokamak reactor at the beginning of the discharge start are presented. The dependence of penetration delay in the magnetic field and vortex e.m.f. on the value of active blanket resistance in tracing the torus is obtained

[en] Correlation of various methods for calculating coefficients of internal and mutual inductance of massive circular coaxial circuits with respect to accuracy and fast response was conducted. Boundaries of applicability of each method were determined and criteria of the choice of the most effective one for one or another particular case were formulated. The structure of universal algorithm providing calculation of inductance coefficients of coaxial circuits in the general case of trapezoidal cross section with assigned accuracy degree was described

[en] Zero-dimensional two-temperature model of energy balance in tokamak plasma, taking account of main limitations on plasma parameters, is described. Results of model correlations with JET device experiments show the satisfactory agreement of results at the stage of break-down, current increase, current plateau and additional plasma heating. 14 refs.; 7 figs

[en] Intensive reconstruction of poloidal magnetic field in tokamak reactor blancket area takes place in the plasma current disruption mode and electrodynamic loads on the blanket structures reach their extreme values. Bound loop approach is applied for analysis of transitional electromagnetic processes, occuring in tokamak reactor azimuth-sectioned blanket under plasma current disruption. Parametric dependence of eddy current maximum values, electric voltage between the blanket sectors and the main electrodynamic loads on the active resistance of bellowses and blanket sector inside walls and on the typical time of plasma current decay, is presented

[en] A method of coupled circuits has been applied for numerical simulation of non-stationary electromagnetic processes. An axial-symmetric calculational model intended for analysis of most intensive electromagnetic processes taking place in structural elements of the tokamak reactor during reconstruction of a poloidal magnetic field is considered. Solution of the Cauchy problem for the obtained system of linear differential equations is determined by numerical integration with application of the implicit Eiler method. Problems of automatic choice of integration step are considered, and comparison with the results of solving the model problem is conducted

[en] The paper deals with numerical simulation of plasma vertical position stabilization in ITER. The calculations are performed using EDDY C-2 code by the method of direct numerical simulation of transient electromagnetic processes taking into account the evolution of plasma position, cross-section shape and full plasma current. When simulating free vertical plasma drift in ITER with twin passive stabilization loops, it was shown that account of the effects of cross-section deformation and plasma current alternations results in almost two fold degradation of passive stabilization parameters as compared to the calculations for 'rigid displacement' model. In terms of methodology, the account of the effects of cross section deformation and plasma current alternations requires clarification of the definitions for reverse increment of vertical instability and for stability margin coefficient. The simulation of plasma pinch return to equilibrium position after the closure of control coils allows to assess the required parameters of active control system and demonstrate the effect of screen current reverse in twin loops. The obtained results were used to develop the ITER conceptual design and affected the choice of the concept of twin passive loops and new positron of control coils as the basis approaches. 11 refs.; 12 figs.; 1 tab

[en] Characteristics of a regime with a complex examination of achieving the maximum values of q₁^-1, n, β (qnβ-regime) in a T-10 scale tokamak are considered. Scenarios of coming on such a regime are proposed. The main feature of qnβ-regime consists in a specific flow-through operation regime with powerful sources of particles and energy and powerful system of gas pumping from the divertor. The problem of coordination of particle and energy sources introduced to plasma is of an increased interest in this regime. 7 refs.; 4 figs.; 2 tabs

[en] Dependences of calculated maxima of electrodynamical loads on the vacuum chamber of a tokamak on choice of disruption scenry are considered. The general problem of analysis of electromagnetic properties due to orthogonality of toroidal and poloidal magnetic fields is divided into two independent subproblems. The problem statements and computerized simulations obtained with the help of EDDYC-1 and EDDYC-2 computer programs are presented. 10 refs.; 7 figs.; 1 tab

[en] The results of preliminary consideration of a compact tokamak with a strong magnetic field designed for achievement and investigation of thermonuclear burning are presented. A model of the compact tokamak with ignition with the following parameters: aspect ratio of plasma filament A-5; the large radius of plasma filament 2.2 m; the small radius- 0.44 m; the diverter-poloidal, two-zero; stretch by the vertical 1.7; current in the plasma filament 3.8 MA; plasma density in the burning regime, average 6-8x10¹⁴ cm^-3, on the axis 1-5x10¹⁵ cm^-3; temperature on the axis 10 keV; ignition margin 1-2; heating before ignition by means of ion cyclotron resonance at negligible He³ addition addition, f=104 mHz, P_HF=12 MW; heating duration 3-5 s, is considered. Systems of a poloidal field and HF-heating, a discharge chamber and a power supply system are described. Stress-deformed state as well as strength of the electromagnetic system and discharge chamber are considered

[en] The problem on numerical simulation of nonstationary electromagnetic processes for a dynamic model of the plasma in tokamak is considered; the calculational results of the ITER vacuum chamber when upsetting plasma current of eddy currents, electrodynamic loads and the rate of change in a tangent component of the magnetic field at the OTP superconductor are presented. Shielding operation of the ITER vacuum chamber when starting discharge is calculated. Dependence of the results obtained on the degree of chamber sectioning and electric resistance of its sections and bellows is analysed. 8 refs.; 14 figs.; 1 tab