The paper is devoted to developing methods and systems of identification and kinetic feedback control of burning plasma. Numerical simulations are carried out for ITER parameters. In the approach given plasma column is considered as a nonlinear multi-linked dynamical system. It has space-distributed parameters, input and output constraints (saturations) and is described by a set of coupled differential equations of diffusion type. Plasma-physics code ASTRA has been used for the qualitative investigation of plant internal couplings by means of determining plasma responses of Pfus, ne, Uloop, J(r), q(r), Te, Ti, くp, Pdivertor on test-step actions PNBI, PRF, fuelling, Arseeding. In doing so, one observes two inherent times of plasma parameters change. One of these times is appropriate to the plasma transport time, and the other one is related with the reconstruction of current profile and essentially exceeds the first one (about 2 orders). After transient responses on the test-step actions the output signals return to nearby vicinity of their initial values. This phenomenon shows the existence of a self-compensation of input actions by internal couplings of burning plasma. The 4-loops control system containing separate feedback channels is used to stabilize Pfus, ne, Uloop, Pdivertor simultaneously with corresponding plant input actions PNBI, fuelling, PRF, Arseeding. Simulations on ASTRA code show that proportional regulations in each control channel stabilize output signals around their specified values. The reasonable amount of stabilization accuracy is achieved at the action of impulse disturbances of various natures. The results are compared with the simulations when the feedbacks are disconnected. Therewith the considerable plasma parameters perturbations are observed which sometimes lead to the whole cooling of plasma column. The stabilization without decoupling says about weak internal plant couplings, which permits to apply multivariable diagonal controller without additional external cross-couplings. Sometimes the hierarchical principle of control priorities change is used at the stabilization of the set of output variables. When the control power PNBI saturates the other actuator is automatically connected up to stabilize Pfus and the stabilization loop of that actuator is broken at the same time. Further stages of the work are discussed, which assume applying separate and combined control of radial profiles of ITER plasma basic parameters taking into account technical constraints adopted in the ITER project.