Characterisation and optimisation of the divertor of a next step fusion device

热核实验堆是托卡马克类型的实验装置，其目的是证明聚变能源用于和平目的的科学和技术可行性。它的建设已经确定，由欧洲、日本、俄罗斯、美国、中国和韩国组成的国际伙伴关系即将在法国卡达拉奇开工建设。预计加拿大团体将参与热核实验堆的具体项目。在ITER最重要的物理问题中，功率和粒子控制是关键领域之一，因为偏滤器是等离子体和面向等离子体的材料组件之间的界面，必须在现实的等离子体和技术参数下同时排出功率、氘和氦灰烬。边缘和偏滤器等离子体模型提供了定义和优化这一重要部件及其工作参数的关键。利用最先进的等离子体模拟程序B2-Eirene，对下一步聚变装置ITER的偏滤器的等离子体参数进行了表征，研究了基于各种注入杂质的辐射的改进的偏滤器操作方案，优化了与其他等离子体和对装置的技术约束一致的操作条件，并研究了偏滤器几何形状的改变对偏滤器操作的影响。这项工作将在国际合作框架内进行。

ITER is an experimental device of the tokamak type whose purpose is to demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes. Its construction has been decided and the start of construction in Cadarache, France, by an international partnership consisting of Europe, Japan, Russia, the United States, China, and South Korea is imminent. Canadian groups are expected to participate in specific projects on ITER. Among the most important physics questions for ITER, power and particle control ranks as one of the crucial areas because the divertor, the interface between the plasma and the material plasma-facing components, must simultaneously exhaust the power, the deuterium, and the helium ash at realistic plasma and technological parameters. The key to the definition and optimisation of this vital component and its operating parameters is provided by edge and divertor plasma modelling. Using the state-of-the-art plasma simulation code B2-EIRENE, it is proposed to characterise the plasma parameters of the divertor of a next-step fusion device, ITER, to investigate improved divertor operating scenarios based on the radiation of various injected impurities, to optimise the operating conditions consistent with the other plasma and technological constraints on the device and to investigate the impact of modifications of the divertor geometry. The work will be carried out in a framework of international cooperation.