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Edge plasma control with a Local Island Divertor

使用本地岛偏滤器进行边缘等离子体控制

基本信息

批准号：
11558059
负责人：
KOMORI Akio
金额：
$ 6.85万
依托单位：
National Institute for Fusion Science
依托单位国家：
日本
项目类别：
Grant-in-Aid for Scientific Research (B)
财政年份：
1999
资助国家：
日本
起止时间：
1999 至 2002
项目状态：
已结题

来源：
https://kaken.nii.ac.jp/en/grant/KAKENHI-PROJECT-11558059/
关键词：
Large Helical Device Local island divertor edge plasma control Pumping efficiency Divertor head Buffle plate Compact helical System

项目摘要

Aims of this research project are to develop technical and design studies of a local island divertor (LED) and to realize it in fusion-experiment devices, especially in the Large Helical Device (LHD).The LID is a divertor that uses an m/n=1/1 island formed at the edge region. The outward heat and particle fluxes crossing the island separatrix flow along the field lines to the back of the island, where divertor plates are placed on a divertor head to receive heat and particle loads. The particles recycled there are pumped out by a pumping system. Unlike conventional pump limiters, leading edges of the divertor head are located well inside the island for the standard LID configuration, thereby being protected from the outward heat flux from the core. The principle of the LID has been proved by the experimental study on the Compact Helical System (CHS).In this research project, a comparison between theory and observation was performed at first, using the experimental results measured in CHS and theoretical predictions obtained, for example, by a Monte Carlo neutral-particle simulation code. This provided us critical information on the edge plasma behavior in the heliotron-type device, and helped us to optimize the design of the LID for LHD. Especially, the geometrical design of the divertor head and pumping duct was completed, and a closed divertor configuration was demonstrated to be realized with high pumping efficiency of > 30%. Highly efficient pumping is the key to realizing the high temperature divertor operation, where a divertor plasma with a temperature of a few keV is produced, leading to a significant energy confinement improvement.After the technical studies were finished, the LID was fabricated, and installed in LHD at the end of 2002 fiscal year. Preliminary experiments performed in 2003 suggested the existence of fundamental divertor functions expected for the LID, so that the aims of this research project were achieved.

本研究项目的目的是开展局部岛型分流器（LED）的技术和设计研究，并在核聚变实验装置，特别是大螺旋装置（LHD）中实现。LID是一种分流器，使用在边缘区域形成的m/n=1/1岛。向外的热量和颗粒通量穿过岛状分离矩阵沿场线流向岛状后部，在岛状后部，导流板放置在导流头上以接收热量和颗粒负荷。在那里回收的颗粒由泵送系统泵出。与传统的泵限流器不同的是，对于标准的LID配置，导流器头部的前缘位于岛内，从而免受来自岩心的向外热流的影响。在紧凑螺旋系统（CHS）上的实验研究证实了LID的原理。在本研究项目中，首先将理论与观测进行比较，使用CHS测量的实验结果和理论预测，例如通过Monte Carlo中性粒子模拟代码。这为我们提供了关于heliotron型器件中边缘等离子体行为的关键信息，并帮助我们优化LHD的LID设计。特别是完成了导流器头部和抽风道的几何设计，实现了闭式导流器配置，泵送效率高达bbb30 %。高效抽运是实现高温导流器运行的关键，在高温导流器中产生温度为几keV的等离子体，从而显著改善能量约束。在技术研究完成后，LID被制造出来，并在2002财政年度末安装在LHD中。2003年进行的初步实验表明，存在预期的LID基本分流功能，从而实现了本研究项目的目标。