Аннотация:In modern vertically elongated tokamaks it iscritically important to maintain plasma near the first wall at thediverter phase of a plasma scenario. The reason for this is toallow plasma equilibrium reconstruction in real time, based onthe external magnetic measurements of the plasma. This papersuggests a simulation approach to obtain plasma position,current, and shape control, with a plasma equilibriumreconstruction code used in feedback. The new basic idea ofsuch a simulation is to combine scenario signals with the datacoming from the linear model based on tokamak experimentaldata. This sum comes to the reconstruction code, whichreconstructs the separatrix location and gaps between thetokamak first wall and the separatrix itself. Using the exampleof the functioning spherical tokamak Globus-M (Ioffe Institute,S-Petersburg, Russia), we show the results of simulation ofplasma gaps in a closed-loop control system with an original H∞LPV plasma shape controller at upper X-point of the plasmamagnetic configuration. The simulation approach may beapplied to any tokamak elongated in the vertical direction toadjust plasma shape control systems before application inexperiments.