No abstract

The Zero-dimensional system model has been widely used for predicting and analyzing plasma performance in fusion reactors and designing next-generation tokamaks. These models can rapidly perform various parameter scans, which can be used for device reference operation point design and to prepare for more accurate One-dimensional numerical simulations. They can also be used to predict device operational parameters and heating/current drive conditions, providing a quick reference for experimental design. However, relying on physical approximations and empirical formulas can lead to significant systematic errors. This paper introduces a plasma equilibrium program to make the main plasma profile parameters and their calculations based on magnetic surface information. It also improves the bootstrap current calculation by introducing the relationship between the bootstrap current coefficient of the Sauter model and the collision rate change. The improved model was validated using experimental results from EAST, and the results of the zero-dimensional system model calculations were found to be consistent with the results of kinetic equilibrium analysis. Based on the improved model and existing experimental results, the analysis and prediction of the required heating/current drive power and achievable normalized beta for steady-state, long-pulse operation of the 500kA plasma current on EAST were carried out. The calculation results show that EAST can achieve steady-state operation of the 500kA plasma current with bootstrap current fraction over 50% within the parameter range of 7-9.5MW heating/driving power, <i>H</i>₉₈ ~1.25-1.35, and <i>f_nG</i>~0.9. Additionally, to maintain the total non-inductive current, the total heating/current drive power is highly sensitive to plasma confinement and density, which are the most effective ways to increase the bootstrap current fraction and reduce the peak heat loads on the divertor. Improving plasma confinement is the most effective way to achieve high bootstrap current fractions and reduce the peak heat load on the divertor. The paper also analyzes the effect of different heating power ratios on the bootstrap current, showing that adjusting the power ratio can change the bootstrap current fraction. The paper further analyzes the long-pulse operating region of EAST with a plasma current of 500 kA. Within the range of 9.5 MW total heating/current driving power, <i>H</i>₉₈~1.0-1.4, and normalized electron density <i>f_nG</i> ~0.8-1.0, high-performance long-pulse or fully non-inductive steady-state operation can be achieved, supporting research on the physics of ITER and CFETR steady-state operation modes. In general, improving the plasma confinement performance can achieve fully non-inductive operation at lower heating/driving power while maintaining the same plasma parameters, and expand the plasma operating regime, which is the most effective way to achieve high-parameter steady-state operation of the plasma.