Title :
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
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;
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
DOI :
10.1109/FUSION.2007.4337925
