Plasma wall interaction and tritium retention in TFTR

C. H. Skinner, E. Amarescu, G. Ascione, W. Blanchard, C. W. Barnes, S. H. Batha, Michael 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

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
StatePublished - Feb 11 1997
Externally publishedYes

Fingerprint

Tritium
Beam plasma interactions
tritium
Fusion reactions
fusion
reactors
Plasmas
Deuterium
deuterium
interactions
cleaning
Cleaning
Glow discharges
conditioning
recycling
Lithium
pellets
glow discharges
Discharge (fluid mechanics)
plasma jets

Keywords

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

ASJC Scopus subject areas

  • Electronic, Optical and Magnetic Materials

Cite this

Skinner, C. H., Amarescu, E., Ascione, G., Blanchard, W., Barnes, C. W., Batha, S. H., ... Von Goeler, S. (1997). Plasma wall interaction and tritium retention in TFTR. Journal of Nuclear Materials, 241-243, 214-226.

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

In: Journal of Nuclear Materials, Vol. 241-243, 11.02.1997, p. 214-226.

Research output: Contribution to journalArticle

Skinner, CH, Amarescu, E, Ascione, G, Blanchard, W, Barnes, CW, Batha, SH, Beer, M, Bell, MG, Bell, R, Bitter, M, Bretz, NL, Budny, R, Bush, CE, Camp, R, Casey, M, Collins, J, Cropper, M, Chang, Z, Darrow, DS, Duong, HH, Durst, R, Efthimion, PC, Ernst, D, Fisch, N, Fonck, RJ, Fredrickson, E, Fu, G, Furth, HP, Gentile, CA, Gibson, M, Gilbert, J, Grek, B, Grisham, LR, Hammett, G, Hawryluk, RJ, Herrmann, HW, Hill, KW, Hosea, J, Janos, A, Jassby, DL, Jobes, FC, Johnson, DW, Johnson, LC, Kamperschroer, J, Kalish, M, Kugel, H, Langford, J, Langish, S, LaMarche, PH, LeBlanc, B, Levinton, FM, Machuzak, J, Majeski, R, Manikam, J, Mansfield, DK, Mazzucato, E, McGuire, KM, Mika, R, McKee, G, Meade, DM, Medley, SS, Mikkelsen, DR, Mynick, HE, Mueller, D, Nagy, A, Nazikian, R, Ono, M, Owens, DK, Park, H, Paul, SF, Pearson, G, Petrov, M, Phillips, CK, Raftopoulos, S, Ramsey, A, Raucci, R, Redi, MH, Rewoldt, G, Rogers, J, Roquemore, AL, Ruskov, E, Sabbagh, SA, Schilling, G, Schivell, JF, Schmidt, GL, Scott, SD, Sesnic, S, Stratton, BC, Strachan, JD, Stevenson, T, Stotler, DP, Synakowski, E, Takahashi, H, Tang, W, Taylor, G, Tighe, W, Timberlake, JR, Von Halle, A & Von Goeler, S 1997, 'Plasma wall interaction and tritium retention in TFTR', Journal of Nuclear Materials, vol. 241-243, pp. 214-226.
Skinner CH, Amarescu E, Ascione G, Blanchard W, Barnes CW, Batha SH et al. Plasma wall interaction and tritium retention in TFTR. Journal of Nuclear Materials. 1997 Feb 11;241-243:214-226.
Skinner, C. H. ; Amarescu, E. ; Ascione, G. ; Blanchard, W. ; Barnes, C. W. ; Batha, S. H. ; Beer, Michael ; 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. ; Duong, H. H. ; Durst, R. ; Efthimion, P. C. ; Ernst, D. ; Fisch, N. ; Fonck, R. J. ; Fredrickson, E. ; Fu, G. ; Furth, H. P. ; Gentile, C. A. ; Gibson, M. ; Gilbert, J. ; Grek, B. ; Grisham, L. R. ; Hammett, G. ; Hawryluk, R. J. ; Herrmann, H. W. ; Hill, K. W. ; Hosea, J. ; Janos, A. ; Jassby, D. L. ; Jobes, F. C. ; Johnson, D. W. ; Johnson, L. C. ; Kamperschroer, J. ; Kalish, M. ; Kugel, H. ; Langford, J. ; Langish, S. ; LaMarche, P. H. ; LeBlanc, B. ; Levinton, F. M. ; Machuzak, J. ; Majeski, R. ; Manikam, J. ; Mansfield, D. K. ; Mazzucato, E. ; McGuire, K. M. ; Mika, R. ; McKee, G. ; Meade, D. M. ; Medley, S. S. ; Mikkelsen, D. R. ; Mynick, H. E. ; Mueller, D. ; Nagy, A. ; Nazikian, R. ; Ono, M. ; Owens, D. K. ; Park, H. ; Paul, S. F. ; Pearson, G. ; Petrov, M. ; Phillips, C. K. ; Raftopoulos, S. ; Ramsey, A. ; Raucci, R. ; Redi, M. H. ; Rewoldt, G. ; Rogers, J. ; Roquemore, A. L. ; Ruskov, E. ; Sabbagh, S. A. ; Schilling, G. ; Schivell, J. F. ; Schmidt, G. L. ; Scott, S. D. ; Sesnic, S. ; Stratton, B. C. ; Strachan, J. D. ; Stevenson, T. ; Stotler, D. P. ; Synakowski, E. ; Takahashi, H. ; Tang, W. ; Taylor, G. ; Tighe, W. ; Timberlake, J. R. ; Von Halle, A. ; Von Goeler, S. / Plasma wall interaction and tritium retention in TFTR. In: Journal of Nuclear Materials. 1997 ; Vol. 241-243. pp. 214-226.
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TY - JOUR

T1 - Plasma wall interaction and tritium retention in TFTR

AU - Skinner, C. H.

AU - Amarescu, E.

AU - Ascione, G.

AU - Blanchard, W.

AU - Barnes, C. W.

AU - Batha, S. H.

AU - Beer, Michael

AU - Bell, M. G.

AU - Bell, R.

AU - Bitter, M.

AU - Bretz, N. L.

AU - Budny, R.

AU - Bush, C. E.

AU - Camp, R.

AU - Casey, M.

AU - Collins, J.

AU - Cropper, M.

AU - Chang, Z.

AU - Darrow, D. S.

AU - Duong, H. H.

AU - Durst, R.

AU - Efthimion, P. C.

AU - Ernst, D.

AU - Fisch, N.

AU - Fonck, R. J.

AU - Fredrickson, E.

AU - Fu, G.

AU - Furth, H. P.

AU - Gentile, C. A.

AU - Gibson, M.

AU - Gilbert, J.

AU - Grek, B.

AU - Grisham, L. R.

AU - Hammett, G.

AU - Hawryluk, R. J.

AU - Herrmann, H. W.

AU - Hill, K. W.

AU - Hosea, J.

AU - Janos, A.

AU - Jassby, D. L.

AU - Jobes, F. C.

AU - Johnson, D. W.

AU - Johnson, L. C.

AU - Kamperschroer, J.

AU - Kalish, M.

AU - Kugel, H.

AU - Langford, J.

AU - Langish, S.

AU - LaMarche, P. H.

AU - LeBlanc, B.

AU - Levinton, F. M.

AU - Machuzak, J.

AU - Majeski, R.

AU - Manikam, J.

AU - Mansfield, D. K.

AU - Mazzucato, E.

AU - McGuire, K. M.

AU - Mika, R.

AU - McKee, G.

AU - Meade, D. M.

AU - Medley, S. S.

AU - Mikkelsen, D. R.

AU - Mynick, H. E.

AU - Mueller, D.

AU - Nagy, A.

AU - Nazikian, R.

AU - Ono, M.

AU - Owens, D. K.

AU - Park, H.

AU - Paul, S. F.

AU - Pearson, G.

AU - Petrov, M.

AU - Phillips, C. K.

AU - Raftopoulos, S.

AU - Ramsey, A.

AU - Raucci, R.

AU - Redi, M. H.

AU - Rewoldt, G.

AU - Rogers, J.

AU - Roquemore, A. L.

AU - Ruskov, E.

AU - Sabbagh, S. A.

AU - Schilling, G.

AU - Schivell, J. F.

AU - Schmidt, G. L.

AU - Scott, S. D.

AU - Sesnic, S.

AU - Stratton, B. C.

AU - Strachan, J. D.

AU - Stevenson, T.

AU - Stotler, D. P.

AU - Synakowski, E.

AU - Takahashi, H.

AU - Tang, W.

AU - Taylor, G.

AU - Tighe, W.

AU - Timberlake, J. R.

AU - Von Halle, A.

AU - Von Goeler, S.

PY - 1997/2/11

Y1 - 1997/2/11

N2 - 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.

AB - 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.

KW - Helium exhaust and control

KW - TFTR

KW - Tritium inventory and economy

KW - Wall conditioning

KW - Wall particle retention

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