导流器冲蚀与蒸汽屏蔽实验(DEVeX)综述与现状

T. Gray, M.J. Williams, D. Ruzic
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引用次数: 5

摘要

导流器侵蚀和蒸汽屏蔽实验(DEVeX)正在伊利诺伊大学厄巴纳-香槟分校进行,旨在研究入射高焓等离子体流如何与等离子体面向组件(pfc)代表的目标材料相互作用。DEVeX包括一个锥形的,用于压缩和驱逐与融合中断相关的等离子体,如边缘局域模式(elm)。通过雪犁模型对等离子体压缩进行建模,表明预期等离子体密度为1021 m-3,温度约为1 keV,持续时间为100 mus。DEVeX的设计和性能概述将与目前的结果一起提出。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Overview and Status of the Divertor Erosion and Vapor shielding eXperiment (DEVeX)
The Divertor Erosion and Vapor shielding experiment (DEVeX) is being constructed at the University of Illinois at Urbana-Champaign to study how incident high enthalpy plasma flows interact with target materials representative of plasma facing components (PFCs). DEVeX consists of a conical, theta-pinch used to compress and expel plasmas relevant to fusion disruptions such as edge localized modes (ELMs). Modeling of the plasma compression, via a snow-plow model, shows expected plasma densities of 1021 m-3 with a temperature of approximately 1 keV for a duration of 100 mus. An overview of the design and performance of DEVeX will be presented along with current results.
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