Surface impurity removal from DIII-D graphite tiles by boron carbide grit blasting

Abstract

During the latter half of 1992, the DIII-D tokamak at General Atomics (GA) underwent several modifications of its interior. One of the major tasks involved the removal of accumulated metallic impurities from the surface of the graphite tiles used to line the plasma facing surfaces inside of the tokamak. Approximately 1500 graphite tiles and 100 boron nitride tiles from the tokamak were cleaned to remove the metallic impurities. The cleaning process consisted of several steps: the removed graphite tiles were permanently marked, surface blasted using boron carbide (B/sub 4/C) grit media (approximately 37 /spl mu/m. diam.), ultrasonically cleaned in ethanol to remove loose dust, and outgassed at 1000/spl deg/C. Tests were done using graphite samples and different grit blaster settings to determine the optimum propellant and abrasive media pressures to remove a graphite layer approximately 40-50 /spl mu/m deep and yet produce a reasonably smooth finish. EDX and beta-backscattering measurements revealed that the blasting technique reduced the surface Ni, Cr, and Fe impurity levels to those of virgin graphite. Auger analysis of blasted tile samples does not show surface impurities within the first few atomic layers. An estimate of the depth of surface roughness due to the B/sub 4/C abrasive action is /spl plusmn/20 /spl mu/m. In addition to the surface impurity removal, tritium monitoring was performed throughout the cleaning process. A bubbler system was set up to monitor the tritium level in the exhaust gas from the grit blaster unit. Surface wipes were also performed on over 10% of the tiles. Typical surface tritium concentrations of the tiles were reduced from about 500 dpm/100 cm/sup 2/ to less than 80 dpm/100 cm/sup 2/ following the cleaning. This tile conditioning, and the installation of additional graphite tiles to cover a high fraction of the metallic plasma facing surfaces, has substantially reduced metallic impurities in the plasma discharges which has allowed rapid recovery from a seven-month machine opening and regimes of enhanced plasma energy confinement to be more readily obtained. Safety issues concerning blaster operator exposure to carcinogenic metals and radioactive tritium will also be addressed.