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

Travis K. Gray, Michael J. Williams, David N. Ruzic

Research output: Chapter in Book/Report/Conference proceedingConference contribution

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, thetapinch 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 μs. An overview of the design and performance of DEVeX will be presented along with current results.

Original languageEnglish (US)
Title of host publicationProceedings of the 22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07
DOIs
StatePublished - Dec 1 2007
Event22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07 - Albuquerque, NM, United States
Duration: Jun 17 2007Jun 21 2007

Publication series

NameProceedings - Symposium on Fusion Engineering

Other

Other22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07
CountryUnited States
CityAlbuquerque, NM
Period6/17/076/21/07

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

Fingerprint Dive into the research topics of 'Overview and status of the Divertor Erosion and Vapor shielding eXperiment (DEVeX)'. Together they form a unique fingerprint.

  • Cite this

    Gray, T. K., Williams, M. J., & Ruzic, D. N. (2007). Overview and status of the Divertor Erosion and Vapor shielding eXperiment (DEVeX). In Proceedings of the 22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07 [4337925] (Proceedings - Symposium on Fusion Engineering). https://doi.org/10.1109/FUSION.2007.4337925