DocumentCode
3129815
Title
Experimental study of gas flow through curved tubes in support of disruption mitigation experiments in DIII-D
Author
Combs, S.K. ; Baylor, L.R. ; Foust, C.R. ; Jernigan ; Tsai, C.C.
Author_Institution
Oak Ridge Nat. Lab., TN, USA
fYear
2003
fDate
14-17 Oct. 2003
Firstpage
470
Lastpage
473
Abstract
High-pressure gas injection has been shown to be an effective disruption mitigation technique in the DIII-D tokamak, offering dramatic reductions in localized power deposition and forces to the internal components due to halo currents. To date, the gas (Ar, Ne, He, or H2) has been injected from the magnetic low-field side of the machine through close-coupled stainless steel tubes, with relatively high gas load per shot (up to 4000 torr-L in ≈10 ms). Another option for high-pressure gas injection in DIII-D is to utilize curved guide tubes similar to those presently used for magnetic high-field side pellet injection with exit ports on the inner wall. To demonstrate the feasibility of this option, an experimental study with different tube diameters and configurations has been carried out in the laboratory. The test results indicate that sufficiently high gas flows can be delivered through the curved guide tubes as long as the tube bore is not too restrictive (≥7.5-mm diam). The experimental results are presented and discussed relative to the disruption mitigation experiments in DIII-D.
Keywords
Tokamak devices; argon; helium; hydrogen; neon; plasma beam injection heating; plasma flow; plasma toroidal confinement; Ar; DIII-D tokamak; H2; He; Ne; close-coupled stainless steel tubes; curved guide tubes; curved tubes; disruption mitigation experiments; exit ports; gas flow; halo currents; high-pressure gas injection; inner wall; internal components; localized power deposition; localized power forces; magnetic high-field side pellet injection; magnetic low-field side pellet injection; relatively high gas load; tube bore; tube diameters; Argon; Fluid flow; Helium; Laboratories; Plasma confinement; Plasma sources; Steel; Testing; Tokamaks; Valves;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on
Print_ISBN
0-7803-7908-X
Type
conf
DOI
10.1109/FUSION.2003.1426685
Filename
1426685
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