Plasma wall interaction and tritium retention in TFTR

  • C. H. Skinner
  • , E. Amarescu
  • , G. Ascione
  • , W. Blanchard
  • , C. W. Barnes
  • , S. H. Batha
  • , M. Beer
  • , M. G. Bell
  • , R. Bell
  • , M. Bitter
  • , N. L. Bretz
  • , R. Budny
  • , C. E. Bush
  • , R. Camp
  • , M. Casey
  • , J. Collins
  • , M. Cropper
  • , Z. Chang
  • , D. S. Darrow
  • , H. H. Duong
  • R. Durst, P. C. Efthimion, D. Ernst, N. Fisch, R. J. Fonck, E. Fredrickson, G. Fu, H. P. Furth, C. A. Gentile, M. Gibson, J. Gilbert, B. Grek, L. R. Grisham, G. Hammett, R. J. Hawryluk, H. W. Herrmann, K. W. Hill, J. Hosea, A. Janos, D. L. Jassby, F. C. Jobes, D. W. Johnson, L. C. Johnson, J. Kamperschroer, M. Kalish, H. Kugel, J. Langford, S. Langish, P. H. LaMarche, B. LeBlanc, F. M. Levinton, J. Machuzak, R. Majeski, J. Manikam, D. K. Mansfield, E. Mazzucato, K. M. McGuire, R. Mika, G. McKee, D. M. Meade, S. S. Medley, D. R. Mikkelsen, H. E. Mynick, D. Mueller, A. Nagy, R. Nazikian, M. Ono, D. K. Owens, H. Park, S. F. Paul, G. Pearson, M. Petrov, C. K. Phillips, S. Raftopoulos, A. Ramsey, R. Raucci, M. H. Redi, G. Rewoldt, J. Rogers, A. L. Roquemore, E. Ruskov, S. A. Sabbagh, G. Schilling, J. F. Schivell, G. L. Schmidt, S. D. Scott, S. Sesnic, B. C. Stratton, J. D. Strachan, T. Stevenson, D. P. Stotler, E. Synakowski, H. Takahashi, W. Tang, G. Taylor, W. Tighe, J. R. Timberlake, A. Von Halle, S. Von Goeler

Research output: Contribution to journalArticlepeer-review

3 Scopus citations

Abstract

The Tokamak Fusion Test Reactor (TFTR) has been operating safely and routinely with deuterium-tritium fuel for more than two years. In this time, TFTR has produced a number of record breaking results including core fusion power, ∼ 2 MW/m3, comparable to that expected for ITER. Advances in wall conditioning via lithium pellet injection have played an essential role in achieving these results. Deuterium-tritium operation has also provided a special opportunity to address the issues of tritium recycling and retention. Tritium retention over two years of operation was approximately 40%. Recently the in-torus tritium inventory was reduced by half through a combination of glow discharge cleaning, moist-air soaks, and plasma discharge cleaning. The tritium inventory is not a constraint in continued operations. Recent results from TFTR in the context of plasma wall interactions and deuterium-tritium issues are presented.

Original languageEnglish
Pages (from-to)214-226
Number of pages13
JournalJournal of Nuclear Materials
Volume241-243
DOIs
StatePublished - 11 Feb 1997

Keywords

  • Helium exhaust and control
  • TFTR
  • Tritium inventory and economy
  • Wall conditioning
  • Wall particle retention

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