transport simulation;
integrated simulation code;
PLATO;
tokamak;
power balance;
D O I:
10.1585/pfr.16.1403093
中图分类号:
O35 [流体力学];
O53 [等离子体物理学];
学科分类号:
070204 ;
080103 ;
080704 ;
摘要:
Transport simulations using the integrated code TASK are performed on the PLATO tokamak to forecast plasma performance. For transport simulations considering the experimental conditions, MHD equilibria are obtained by taking into account the external coil current condition. Dependences of the plasma parameters on externally controllable quantities in the experiment, such as the amount of particle fuel and values of the external coil currents, exhibit an increase on the order of 10% in the ion temperature without direct ion heating. (C) 2021 The Japan Society of Plasma Science and Nuclear Fusion Research