Tritium retention and clean-up in JET

Autor: P. D. Morgan, P.D Brennan, J.K. Ehrenberg, P Schild, F.B. Marcus, A Rossi, R Pearce, J. How, J. Orchard, J.P. Coad, Philip Andrew, B. Schunke, H.S. Jensen, D. Stork, R Lässer, M Pick, A. Peacock, A. Gibson, M. Gadeberg, R.D. Monk, O.N. Jarvis, D. L. Hillis
Rok vydání: 1999
Předmět:
Zdroj: Fusion Engineering and Design. 47:233-245
ISSN: 0920-3796
Popis: During 1997 JET operation with D-T plasmas, 35 g of tritium were introduced into the torus, mainly by gas puffing. It was found that during this period, the torus tritium inventory would accumulate at a rate of about 40% of the input. After tritium operation ceased, the experimental program continued with deuterium- and hydrogen-fuelled experiments, during which time the tritium inventory decreased to about 17% of the total input. Techniques aimed at detritiation of the torus included methods using deuterium gas (such as deuterium pulsing) which were used in the middle of the experimental campaign, and methods which could adversely affect the torus vacuum conditions (such as air purges) which were reserved for the period after the experimental campaign. Whilst it was found that the plasma tritium fraction could be reduced to below the 1% level in a few days, the tritium inventory reached a virtually steady level of about 6 g by the end of the campaign.
Databáze: OpenAIRE