• Title of article

    Tritium retention and clean-up in JET

  • Author/Authors

    Andrew ، نويسنده , , P and Brennan، نويسنده , , P.D and Coad، نويسنده , , J.P and Ehrenberg?، نويسنده , , J and Gadeberg، نويسنده , , M and Gibson، نويسنده , , A and Hillis، نويسنده , , D.L and How?، نويسنده , , J and Jarvis، نويسنده , , O.N and Jensen?، نويسنده , , H and L?sser?، نويسنده , , R and Marcus?، نويسنده , , F and Monk?، نويسنده , , R and Morgan، نويسنده , , P and Orchard، نويسنده , , J and Peacock?، نويسنده , , A and Pick، نويسنده , , M and Rossi، نويسنده , , A and Schild، نويسنده , , P and Schunke?، نويسنده , , B and Stork، نويسنده , , D and Pearce، نويسنده , , R، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 1999
  • Pages
    13
  • From page
    233
  • To page
    245
  • Abstract
    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.
  • Keywords
    torus , Tritium retention , JET
  • Journal title
    Fusion Engineering and Design
  • Serial Year
    1999
  • Journal title
    Fusion Engineering and Design
  • Record number

    2350779