Comparative study of boron and neon injections on divertor heat fluxes using SOLPS-ITER simulations

Based on the EAST equilibrium,the effects of boron(B)and neon(Ne)injected at different locations on the target heat load,and the distributions of B and Ne particles were investigated by transport code SOLPS-ITER.It was found that the B injection was more sensitive to the injection location for heat flux control than impurity Ne.The high electron and ion densities near the inner target in the discharge with impurity B injected from over X-point(R1)led to plasma detachment only at the inner target,and the localized B ions in the cases with injection from outer target location(R2)and upstream location(R3)led to far-SOL detachment at the outer target,but not at the inner target.In contrast,for Ne,the spatial distributions of Ne ions and electrons were found to be similar in all the cases at the three injection locations,and the detached plasma was achieved at the inner target and the electron temperature was reduced at the outer target.For locations R2 and R3,impurity B showed a more pronounced effect on the heat flux at the far-SOL of the outer target.Further analysis indicated that Ne atoms came mainly from the recycling sources,whereas B atoms came mainly from injection,and that their distinct atomic distributions resulted from the difference in the ionization threshold and ionization mean free path.In addition,the radiation proportion of B in the divertor region was larger than that of Ne when the total radiation power was similar,which suggests that B has less influence on the core region.

Fuel recycling feedback control via real-time boron powder injection in EAST with full metal wall

A feedback control of fuel recycling via real-time boron powder injection,addressing the issue of continuously increasing recycling in long-pulse plasma discharges,has been successfully developed and implemented on EAST tokamak.The feedback control system includes four main parts:the impurity powder dropper(IPD),a diagnostic system measuring fuel recycling level represented by D_(α)emission,a plasma control system(PCS)implementing the Proportional Integral Derivative(PID)algorithm,and a signal converter connecting the IPD and PCS.Based on this control system,both active control and feedback control experiments have recently been performed on EAST with a full metal wall.The experimental results show that the fuel recycling can be gradually reduced to lower level as PCS control voltage increases.In the feedback control experiments,it is also observed that the D_(α)emission is reduced to the level below the target D_(α)value by adjusting boron injection flow rate,indicating successful implementation of the fuel recycling feedback control on EAST.This technique provides a new method for fuel recycling control of long pulse and high parameter plasma operations in future fusion devices.