DocumentCode :
2732990
Title :
Upgrade of the DIII-D vacuum vessel protection system
Author :
Hollerbach, M.A. ; Lee, R.L. ; Smith, J.P. ; Taylor, P.L.
Author_Institution :
Gen. Atomics, San Diego, CA, USA
Volume :
2
fYear :
1993
fDate :
11-15 Oct 1993
Firstpage :
1185
Abstract :
An upgrade of the General Atomics DIII-D tokamak armor protection system has been completed. The upgrade consisted of armoring the outer wall and the divertor gas baffle with monolithic graphite tiles and cleaning the existing floor, ceiling, and inner wall tiles to remove any deposited impurity layer from the tile surfaces. The new tiles replace the graphite tiles used as local armor for neutral beam shine through, three graphite poloidal back-up limiter bands, and miscellaneous Inconel protection tiles. The total number of tiles increased from 1636 to 3200 and corresponding vessel coverage from 40% to 90%. A new, graphite armored, toroidally continuous, gas baffle between the outer wall and the biased divertor ring was installed in order to accommodate the cryocondensation pump that was installed in parallel with the outer wall tiles. To eliminate a source of copper in the plasma, GRAFOIL gaskets replaced the copper felt metal gaskets previously used as a compliant heat transfer interface between the inertially cooled tiles and the vessel wall. GRAFOIL, an exfoliated, flexible graphite material from Union Carbide, Inc., was used between each tile and the vessel wall and also between each tile and its hold-down hardware. Testing was performed to determine the mechanical compliance, thermal conductance, and vacuum characteristics of the GRAFOIL material. To further decrease the quantity of high Z-materials exposed to the plasma, the 1636 existing graphite tiles were identified, removed, and grit blasted to eliminate a thin layer of deposited metals which included nickel, chromium, and molybdenum. Prior to any processing, a selected set of tiles was tested for radioactivity, including tritium contamination. The tiles were grit blasted in a negative-pressure blasting cabinet using 37 μm boron carbide powder as the blast media and dry nitrogen as the propellant. A 30 to 50 μm-thick layer was removed from the surfaces of each tile. The tiles were cleaned in an ultrasonic alcohol bath and vacuum baked to 1000°C prior to reinstallation. The installation of the graphite armor and gas baffle and the grit blasting of the tiles was performed in August 1992 through January 1993. Initial operational experience with the new armor system is summarized
Keywords :
Tokamak devices; fusion reactor materials; fusion reactor safety; fusion reactors; 1000 C; Cu felt metal gaskets; DIII-D tokamak armor protection system; DIII-D vacuum vessel protection system upgrade; GRAFOIL gaskets; biased divertor ring; ceiling cleaning; compliant heat transfer interface; cryocondensation pump; deposited impurity layer removal; divertor gas baffle; exfoliated flexible graphite material; floor cleaning; graphite armored toroidally continuous gas baffle; graphite poloidal back-up limiter bands; grit blasting; hold-down hardware; inner wall tile cleaning; miscellaneous Inconel protection tiles; monolithic graphite tiles; neutral beam shine; thermal conductance; ultrasonic alcohol bath cleaning; vacuum characteristics; Atomic layer deposition; Cleaning; Conducting materials; Copper; Gaskets; Plasma materials processing; Protection; Tiles; Tokamaks; Vacuum systems;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
Conference_Location :
Hyannis, MA
Print_ISBN :
0-7803-1412-3
Type :
conf
DOI :
10.1109/FUSION.1993.518534
Filename :
518534
Link To Document :
بازگشت