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. DuongR. 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 journalArticle

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

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

Keywords

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

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    Skinner, C. H., Amarescu, E., Ascione, G., Blanchard, W., Barnes, C. W., Batha, S. H., Beer, M., Bell, M. G., Bell, R., Bitter, M., Bretz, N. L., Budny, R., Bush, C. E., Camp, R., Casey, M., Collins, J., Cropper, M., Chang, Z., Darrow, D. S., ... Von Goeler, S. (1997). Plasma wall interaction and tritium retention in TFTR. Journal of Nuclear Materials, 241-243, 214-226. https://doi.org/10.1016/s0022-3115(96)00506-5