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

Author

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

Author_Institution

Univ. of Illinois, Urbana

fYear

2007

fDate

17-21 June 2007

Firstpage

1

Lastpage

4

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.

Keywords

fusion reactor design; fusion reactor divertors; fusion reactor targets; pinch effect; plasma density; plasma flow; plasma instability; plasma temperature; DEVeX design; Illinois University; divertor erosion; edge localized modes; fusion disruptions; high enthalpy plasma flow; plasma compression; plasma density; plasma facing components; plasma temperature; snow-plow model; target materials; theta-pinch; vapor shielding experiment; Coaxial components; Kinetic energy; Plasma accelerators; Plasma density; Plasma materials processing; Plasma measurements; Plasma simulation; Plasma sources; Plasma temperature; Tokamaks;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 2007. SOFE 2007. 2007 IEEE 22nd Symposium on

Conference_Location

Albuquerque, NM

Print_ISBN

978-1-4244-1193-1

Electronic_ISBN

978-1-4244-1194-8

Type

conf

DOI

10.1109/FUSION.2007.4337925

Filename

4337925