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

ITER是一种托卡马克式的实验装置，其目的是证明聚变能用于和平目的的科学和技术可行性。由欧洲、日本、俄罗斯、美国、中国和韩国组成的国际合作伙伴已经决定在法国的卡达拉什开始建设。加拿大的团体有望参与ITER的具体项目。在ITER最重要的物理问题中，功率和粒子控制被列为关键领域之一，因为分流器（等离子体和面向等离子体的材料组件之间的界面）必须在实际的等离子体和技术参数下同时耗尽功率、氘和氦灰。定义和优化这一重要部件及其操作参数的关键是由边缘和分流器等离子体建模提供的。利用最先进的等离子体模拟代码B2-EIRENE，提出表征下一步聚变装置ITER的转流器的等离子体参数，以研究基于各种注入杂质辐射的改进转流器操作方案，优化与设备上其他等离子体和技术限制一致的操作条件，并研究修改转流器几何形状的影响。这项工作将在国际合作的框架内进行。

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.