未来聚变反应堆中，巨大的热流、粒子流在靶板上的沉积宽度仅为毫米量级，这将严重侵蚀靶板材料，破坏聚变产生条件，威胁装置运行安全，是当前聚变界急需解决的一个重大瓶颈问题。本项目将利用最近在国内外聚变装置上发现的粒子流在靶板附近由ExB漂移引起的自发分流现象，探索主动调控靶板区域热流、粒子流分布的新方法以及延长靶板材料寿命的可行机制。国际热核聚变实验堆ITER的设计并未考虑到这一物理效应。本项目将依托安徽省重点实验室EAST全超导托卡马克，并联合美国DIII-D托卡马克装置，针对这种自发分流现象的形成机理开展实验、理论和模拟研究，揭示决定该现象形成的关键参量和物理机制；并发展边界充气反馈等调控靶板附近电场的方法，研究其对刮削层参数、H模台基约束性能以及L-H转换功率阈值的影响。该项研究将对我国未来聚变堆CFETR的偏滤器结构、粒子排除和辐射偏滤器运行模式的设计具有重要的指导意义。

In future fusion devices, a mass of heat and particle flux with width only ~1 mm loading on divertor targets will strongly erode the target material, break the fusion condition and impact the safety of the machines themselves. Therefore, it is a bottleneck issue for the community to achieve the fusion energy. Based on the newly discovered spontaneous bifurcation of the particle flux in front of divertor targets, we try to find out a new method to regulate the deposition of heat and particle flux on the targets and a possible way to elongate the life time of the target materials. The research and development of International Thermonuclear Experimental Reactor (ITER) have not considered the effect of the spontaneous bifurcation on the deposition of target heat and particle fluxes. This research project aims to study the underlying physics and key related parameters to this spontaneous bifurcation phenomenon by experiments, theory and numerical simulations in EAST superconducting tokamak, which belong to Anhui key laboratory, and the American DIII-D tokamak. Based on above expected achievements, we will develop the methods of controlling electric field in scrape-off layer, such as feedback-control gas puff, to investigate the influence of ExB drift on the boundary plasma parameters, H-mode pedestal confinement and L-H transition power threshold. These researches and expected outcomes can be a good guideline for divertor and particle pumping design and radiating divertor scenario development on the future China Fusion Engineering Test Reactor (CFETR).