摘要：The efficient and safe operation of large fusion devices strongly relies on the plasma configuration inside the vacuum *** is important to construct the proper plasma equilibrium with a desired plasma *** order to construct the target configuration,a shape constraint module has been developed in the tokamak simulation code（TSC）,which controls the poloidal flux and the magnetic field at several defined control *** is used to construct the double null,lower single null,and quasi-snowflake configurations for the required target shape and calculate the required PF coils *** flexibility and practicability of this method have been verified by the simulated results.

摘要：Vertical displacement event（VDE） is a big challenge to the existing tokamak equipment and that being designed. As a Chinese next-step tokamak, the Chinese Fusion Engineering Test Reactor（CFETR） has to pay attention to the VDE study with full-fledged numerical codes during its conceptual design. The tokamak simulation code（TSC） is a free boundary time-dependent axisymmetric tokamak simulation code developed in PPPL, which advances the MHD equations describing the evolution of the plasma in a rectangular domain. The electromagnetic interactions between the surrounding conductor circuits and the plasma are solved self-consistently. The TokSys code is a generic modeling and simulation environment developed in GA. Its RZIP model treats the plasma as a fixed spatial distribution of currents which couple with the surrounding conductors through circuit equations. Both codes have been individually used for the VDE study on many tokamak devices, such as JT-60U, EAST, NSTX, DIII-D, and ITER. Considering the model differences, benchmark work is needed to answer whether they reproduce each other＇s results correctly. In this paper, the TSC and TokSys codes are used for analyzing the CFETR vertical instability passive and active controls design simultaneously. It is shown that with the same inputs, the results from these two codes conform with each other.