Overview and Status of the Divertor Erosion and Vapor shielding eXperiment (DEVeX)

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

Abstract

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.
导流器冲蚀与蒸汽屏蔽实验(DEVeX)综述与现状
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。
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