等离子体约束区由热输运及粒子输运主导的非线性间歇行为是托卡马克等离子物理研究的重要内容之一。输运研究的目的在于，通过压强、电流密度、旋转速度剖面和等离子体截面形状的综合控制，实现等离子体约束性能的优化。热扩散系数是输运的重要参数之一，它基本反映了等离子的热传递效率，并被认为与等离子体约束时间等重要参数间存在必然联系。但由于托卡马克等离子体的复杂性，目前已有的各种模型都或多或少存在不足，特别是不同装置模型之间难以直接移植。本课题正是针对其研究重要性和现实性，提出一种基于实验和理论相结合的新方法，通过改进诊断、建立相关数据库和设计分析软件，开展符合EAST放电模型的有效热扩散模型（χeff） 研究。本课题目标在于给出EAST热扩散系数与装置尺寸及放电参数之间的关系，并找出可能存在的必然联系的理论机理，为输运研究提供有一定意义的启示。本课题的完成相信同时也将为ITER研究提供丰富的数据基础。

The non-linear phenomena in the confinement zone of plasma dominated by the transport of heat and particles is an important research area of plasma physics. The main aim of transport research is realizing the confinement improvement of plasma by controlling all of profiles such as pressure,current,rotation. The effective thermal diffusivity is one of the most important kinetic properties of plasma in tokamak,and it is believed to be related with energy confinemnt time more or less. For the complexity,no general model can be used in all tokamaks,and even be used to express all the discharged in one device. So in this project, we want to build a model which is suitable for EAST experiment results by a novel method, thus exploring the underlying mechanism of this form which determines confinement place. In addition, key diagnostic and data base will be developed at the same time for the research. This project is also belived to be helpful for ITER research.