2020年1月17日 五室第135期研讨会

2020117 五室第135期研讨会

题  目: Comparisons of different lower divertor geometry candidates for EAST by using SOLPS-ITER simulations

报告人: 贾国章

主持人: 黄跃恒

时 间: 2020年1月17日(星期五)    15:00—16:30

地 点: 6楼中间会议室

摘 要:

Divertor is a critical component in exhausting power and particle fluxes from the hot core plasma for present/future Tokamaks. The geometry shape of divertors can play essential roles in protection of surrounding walls, impurity screening, hydrogen recycling, and pumping. In order to fulfill the requirement of future high-power and long-pulse H-mode discharges over 1000s in EAST, the present lower graphite divertor will be upgraded to a tungsten (W) divertor. The first priority required for the new divertor is relatively lower power loads onto the targets, while sufficient pumping performance for particle control and lower W-sputtering rate are also essential factors. Several related cases are compared in aspects of density threshold for detachment, pumping capability, and power exhaust by using the SOLPS-ITER code suite.

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