EAST H模等离子体中钨杂质聚芯带来的辐射冷却是个严峻的问题。国际装置在长脉冲H模条件下芯部钨杂质控制手段方面的研究仍是空白。EAST是目前唯一具备开展此项研究的装置，而且实验中我们已经观察到电子回旋和4.6GHz低杂波芯部加热对钨杂质聚芯的有效抑制。拟通过本项目的支持，针对EAST中性束及射频波协同加热下钨杂质输运开展系统的实验和机理研究，获得有效控制钨杂质输运的实验手段并理解其背后机理，实现电子回旋和4.6GHz低杂波芯部加热有效控制以NBI加热为主的长脉冲H模等离子体中钨杂质聚芯以及芯部钨杂质含量，帮助EAST获得钨杂质含量较低的增强约束的稳态长脉冲H模等离子体。在EAST这一稳态长脉冲装置上开展芯部钨杂质控制相关的实验和机理研究不仅有助于EAST实现长脉冲高参数的目标，而且对ITER在钨偏滤器条件下的稳态长脉冲运行以及今后聚变反应堆钨第一壁的设计都具有重要的参考意义。

The huge radiation power loss due to tungsten accumulation in H-mode plasma is a big issue to achieve steady-state high performance plasma on EAST tokamak. So far, the study on the experimental approaches to control the tungsten impurity in plasma core during long pulse H-mode discharge can only be demonstrated on EAST tokamak which is capable of long pulse steady-state operation. The effective suppression of tungsten accumulation by central heating with application of electron cyclotron resonance heating (ECRH) and 4.6GHz low hybrid wave (LHW) have been already observed in EAST H-mode plasma. In this proposal, the experimental and theoretical study on tungsten transport in NBI- and RF-heated plasma will be systematically carried out to obtain the experimental approaches to control the tungsten transport and understand the underlying physics. The objective of this proposal is to realize the suppression of tungsten accumulation and control of tungsten content in plasma core during long pulse H-mode plasma with high power NBI by central heating with application of ECRH and 4.6GHz LHW, and to support EAST to achieve steady-state long pulse H-mode with low tungsten level and enhanced confinement. The exploration of study on tungsten accumulation suppression during long pulse H-mode on EAST tokamak is very significative for steady-state operation of ITER with tungsten divertor and design of first wall in future fusion reactor.