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

Fingerprint

Shielding
erosion
shielding
Erosion
Vapors
vapors
Plasmas
Snow plows
plasma compression
plows
Plasma flow
Plasma density
Experiments
snow
magnetohydrodynamic flow
plasma density
Enthalpy
Fusion reactions
fusion
enthalpy

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

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

Overview and status of the Divertor Erosion and Vapor shielding eXperiment (DEVeX). / Gray, Travis K.; Williams, Michael J.; Ruzic, David N.

Proceedings of the 22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07. 2007. 4337925 (Proceedings - Symposium on Fusion Engineering).

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

Gray, TK, Williams, MJ & Ruzic, DN 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, 22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07, Albuquerque, NM, United States, 6/17/07. https://doi.org/10.1109/FUSION.2007.4337925
Gray TK, Williams MJ, Ruzic DN. 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. 2007. 4337925. (Proceedings - Symposium on Fusion Engineering). https://doi.org/10.1109/FUSION.2007.4337925
Gray, Travis K. ; Williams, Michael J. ; Ruzic, David N. / Overview and status of the Divertor Erosion and Vapor shielding eXperiment (DEVeX). Proceedings of the 22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07. 2007. (Proceedings - Symposium on Fusion Engineering).
@inproceedings{92b5e1e84b6a4a74a7963165d6a6d22e,
title = "Overview and status of the Divertor Erosion and Vapor shielding eXperiment (DEVeX)",
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.",
author = "Gray, {Travis K.} and Williams, {Michael J.} and Ruzic, {David N.}",
year = "2007",
month = "12",
day = "1",
doi = "10.1109/FUSION.2007.4337925",
language = "English (US)",
isbn = "1424411947",
series = "Proceedings - Symposium on Fusion Engineering",
booktitle = "Proceedings of the 22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07",

}

TY - GEN

T1 - Overview and status of the Divertor Erosion and Vapor shielding eXperiment (DEVeX)

AU - Gray, Travis K.

AU - Williams, Michael J.

AU - Ruzic, David N.

PY - 2007/12/1

Y1 - 2007/12/1

N2 - 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.

AB - 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.

UR - http://www.scopus.com/inward/record.url?scp=47749109096&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=47749109096&partnerID=8YFLogxK

U2 - 10.1109/FUSION.2007.4337925

DO - 10.1109/FUSION.2007.4337925

M3 - Conference contribution

AN - SCOPUS:47749109096

SN - 1424411947

SN - 9781424411948

T3 - Proceedings - Symposium on Fusion Engineering

BT - Proceedings of the 22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07

ER -