The effects of radial and poloidal E×B drifts in the scrape-off layer （SOL） of a limiter tokamak are studied with a one-dimensional fluid code. The transport equations are solved in the poloidal direction with ...The effects of radial and poloidal E×B drifts in the scrape-off layer （SOL） of a limiter tokamak are studied with a one-dimensional fluid code. The transport equations are solved in the poloidal direction with the radial influxes as the source terms. The simulation results show that in the high recycling regime, the effect of the radial E×B drift on plasma density tends to be stronger than that of the poloidal E × B drift. In the sheath-limited regime, the effects of the radial E × B drift and poloidal E × B drift on plasma density are almost equally important. Considering the influence on the electron temperature, the poloidal E × B drift tends to be more important than the radial E × B drift in both the high recycling regime and sheath-limited regime. For the normal By, the poloidal E × B drift tends to raise the pressure at the low field side while the radial E × B drift favours the high field side. The simulation results also show that the E × B drift influences the asymmetries on the parameter distributions at the high field side and low field side, and the distributions are much more symmetric with the field reversal.展开更多
A major challenge facing the steady-state operation of tokamak fusion reactors is to develop a viable divertor solution with order-of-magnitude increase in power handling capability as compared with present experience...A major challenge facing the steady-state operation of tokamak fusion reactors is to develop a viable divertor solution with order-of-magnitude increase in power handling capability as compared with present experience.A recently developed divertor concept for this end has been tested recently on EAST tokamak through combining the effects of a closed divertor corner and E×B drifts.The E×B drifts in the divertor move particles towards the outer divertor corner area in the scrape-off layer for B×▽B directed away from the divertor,which can significantly enhance the particle concentration there,facilitating divertor detachment.In recent EAST experiments,the effects have been demonstrated where the lowest electron temperature at the divertor plate is obtained with strike point located close to the corner in the horizontal target and with B×▽B away from the divertor.These experimental results are in reasonable agreement with SOLPS-ITER simulations including drift effects,suggesting that the new divertor concept potentially provides a promising divertor solution for long-pulse operations of future tokamak fusion reactors with much higher power fluxes.展开更多
基金supported by National Natural Science Foundation of China (No. 10135020)
文摘The effects of radial and poloidal E×B drifts in the scrape-off layer （SOL） of a limiter tokamak are studied with a one-dimensional fluid code. The transport equations are solved in the poloidal direction with the radial influxes as the source terms. The simulation results show that in the high recycling regime, the effect of the radial E×B drift on plasma density tends to be stronger than that of the poloidal E × B drift. In the sheath-limited regime, the effects of the radial E × B drift and poloidal E × B drift on plasma density are almost equally important. Considering the influence on the electron temperature, the poloidal E × B drift tends to be more important than the radial E × B drift in both the high recycling regime and sheath-limited regime. For the normal By, the poloidal E × B drift tends to raise the pressure at the low field side while the radial E × B drift favours the high field side. The simulation results also show that the E × B drift influences the asymmetries on the parameter distributions at the high field side and low field side, and the distributions are much more symmetric with the field reversal.
基金funded by the National Magnetic Confinement Fusion Program of China(Nos.2019YFE03030000,2019YFE03080500 and 2022YFE03060004)National Natural Science Foundation of China(No.U19A20113)。
文摘A major challenge facing the steady-state operation of tokamak fusion reactors is to develop a viable divertor solution with order-of-magnitude increase in power handling capability as compared with present experience.A recently developed divertor concept for this end has been tested recently on EAST tokamak through combining the effects of a closed divertor corner and E×B drifts.The E×B drifts in the divertor move particles towards the outer divertor corner area in the scrape-off layer for B×▽B directed away from the divertor,which can significantly enhance the particle concentration there,facilitating divertor detachment.In recent EAST experiments,the effects have been demonstrated where the lowest electron temperature at the divertor plate is obtained with strike point located close to the corner in the horizontal target and with B×▽B away from the divertor.These experimental results are in reasonable agreement with SOLPS-ITER simulations including drift effects,suggesting that the new divertor concept potentially provides a promising divertor solution for long-pulse operations of future tokamak fusion reactors with much higher power fluxes.
