Suppression of tritium retention in remote areas of ITER by nonperturbative reactive gas injection

F.L. Tabarés, J.A. Ferreira, A. Ramos, G.J. Rooij, van, J. Westerhout, R. Al, J. Rapp, A. Drenik, M. Mozetic

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Abstract

A technique based on reactive gas injection in the afterglow region of the divertor plasma is proposed for the suppression of tritium-carbon codeposits in remote areas of ITER when operated with carbon-based divertor targets. Experiments in a divertor simulator plasma device indicate that a 4¿¿nm/min deposition can be suppressed by addition of 1¿¿Pa·m3¿s-1 ammonia flow at 10 cm from the plasma. These results bolster the concept of nonperturbative scavenger injection for tritium inventory control in carbon-based fusion plasma devices, thus paving the way for ITER operation in the active phase under a carbon-dominated, plasma facing component background. © 2010 The American Physical Society.
Original languageEnglish
Article number175006
Pages (from-to)175006-1/4
JournalPhysical Review Letters
Volume105
Issue number17
DOIs
Publication statusPublished - 2010

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