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

doi:10.1016/s0022-3115(96)00506-5

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 journal › Article › peer-review

67 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 language	English (US)
Pages (from-to)	214-226
Number of pages	13
Journal	Journal of Nuclear Materials
Volume	241-243
DOIs	https://doi.org/10.1016/s0022-3115(96)00506-5
State	Published - Feb 11 1997
Externally published	Yes

Keywords

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

ASJC Scopus subject areas

Nuclear and High Energy Physics
General Materials Science
Nuclear Energy and Engineering

Access to Document

10.1016/s0022-3115(96)00506-5

Cite this

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

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. https://doi.org/10.1016/s0022-3115(96)00506-5

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title = "Plasma wall interaction and tritium retention in TFTR",

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.",

keywords = "Helium exhaust and control, TFTR, Tritium inventory and economy, Wall conditioning, Wall particle retention",

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

note = "Funding Information: The performance of the deuterium-tritium experiments on TFTR has only been possible through the dedicated efforts by all the staff at Princeton Plasma Physics Laboratory and by participants from national and international laboratories, universities and industry. This work was supported by the US Department of Energy Contract No. DE-AC02-76CH03073.",

year = "1997",

month = feb,

day = "11",

doi = "10.1016/s0022-3115(96)00506-5",

language = "English (US)",

volume = "241-243",

pages = "214--226",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

}

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, M.

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.

N1 - Funding Information: The performance of the deuterium-tritium experiments on TFTR has only been possible through the dedicated efforts by all the staff at Princeton Plasma Physics Laboratory and by participants from national and international laboratories, universities and industry. This work was supported by the US Department of Energy Contract No. DE-AC02-76CH03073.

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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UR - http://www.scopus.com/inward/citedby.url?scp=0031546537&partnerID=8YFLogxK

U2 - 10.1016/s0022-3115(96)00506-5

DO - 10.1016/s0022-3115(96)00506-5

M3 - Article

AN - SCOPUS:0031546537

SN - 0022-3115

VL - 241-243

SP - 214

EP - 226

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

ER -

Plasma wall interaction and tritium retention in TFTR

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Keywords

ASJC Scopus subject areas

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