Measurements of tritium retention and removal on the Tokamak Fusion Test Reactor

C. H. Skinner; W. Blanchard; J. Kamperschroer; P. LaMarche; D. Mueller; A. Nagy; S. Scott; G. Ascione; E. Amarescu; R. Camp; M. Casey; J. Collins; M. Cropper; C. Gentile; M. Gibson; J. Hosea; M. Kalish; J. Langford; S. Langish; R. Mika; D. K. Owens; G. Pearson; S. Raftopoulos; R. Raucci; T. Stevenson; A. Von Halle; D. Voorhees; T. Walters; J. Winston

doi:10.1116/1.580224

Measurements of tritium retention and removal on the Tokamak Fusion Test Reactor

C. H. Skinner
, W. Blanchard
, J. Kamperschroer
, P. LaMarche
, D. Mueller
, A. Nagy
, S. Scott
, G. Ascione
, E. Amarescu
, R. Camp
, M. Casey
, J. Collins
, M. Cropper
, C. Gentile
, M. Gibson
, J. Hosea
, M. Kalish
, J. Langford
, S. Langish
, R. Mika

D. K. Owens, G. Pearson, S. Raftopoulos, R. Raucci, T. Stevenson, A. Von Halle, D. Voorhees, T. Walters, J. Winston

PPPL Engineering

Research output: Contribution to journal › Article › peer-review

39 Scopus citations

Abstract

Recent experiments on the Tokamak Fusion Test Reactor have afforded an opportunity to measure the retention of tritium in a graphite limiter that is subject to erosion, codeposition, and high neutron flux. The tritium was injected by both gas puff and neutral beams. The isotopic mix of hydrogenic recycling was measured spectroscopically and the tritium fraction T/(H+D+T) transiently increased to as high as 75%. Some tritium was pumped out during the experimental run and some removed in a subsequent campaign using various clean-up techniques. While the short term retention of tritium was high, various conditioning techniques were successful in removing ≈8000 Ci and restoring the tritium inventory to a level well below the administrative limit.

Original language	English (US)
Pages (from-to)	3267-3274
Number of pages	8
Journal	Journal of Vacuum Science and Technology A: Vacuum, Surfaces and Films
Volume	14
Issue number	6
DOIs	https://doi.org/10.1116/1.580224
State	Published - 1996

All Science Journal Classification (ASJC) codes

Condensed Matter Physics
Surfaces and Interfaces
Surfaces, Coatings and Films

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10.1116/1.580224

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Skinner, C. H., Blanchard, W., Kamperschroer, J., LaMarche, P., Mueller, D., Nagy, A., Scott, S., Ascione, G., Amarescu, E., Camp, R., Casey, M., Collins, J., Cropper, M., Gentile, C., Gibson, M., Hosea, J., Kalish, M., Langford, J., Langish, S., ... Winston, J. (1996). Measurements of tritium retention and removal on the Tokamak Fusion Test Reactor. Journal of Vacuum Science and Technology A: Vacuum, Surfaces and Films, 14(6), 3267-3274. https://doi.org/10.1116/1.580224

@article{93aee43f3fb44251b9bc787211bcad25,

title = "Measurements of tritium retention and removal on the Tokamak Fusion Test Reactor",

abstract = "Recent experiments on the Tokamak Fusion Test Reactor have afforded an opportunity to measure the retention of tritium in a graphite limiter that is subject to erosion, codeposition, and high neutron flux. The tritium was injected by both gas puff and neutral beams. The isotopic mix of hydrogenic recycling was measured spectroscopically and the tritium fraction T/(H+D+T) transiently increased to as high as 75\%. Some tritium was pumped out during the experimental run and some removed in a subsequent campaign using various clean-up techniques. While the short term retention of tritium was high, various conditioning techniques were successful in removing ≈8000 Ci and restoring the tritium inventory to a level well below the administrative limit.",

author = "Skinner, \{C. H.\} and W. Blanchard and J. Kamperschroer and P. LaMarche and D. Mueller and A. Nagy and S. Scott and G. Ascione and E. Amarescu and R. Camp and M. Casey and J. Collins and M. Cropper and C. Gentile and M. Gibson and J. Hosea and M. Kalish and J. Langford and S. Langish and R. Mika and Owens, \{D. K.\} and G. Pearson and S. Raftopoulos and R. Raucci and T. Stevenson and \{Von Halle\}, A. and D. Voorhees and T. Walters and J. Winston",

year = "1996",

doi = "10.1116/1.580224",

language = "English (US)",

volume = "14",

pages = "3267--3274",

journal = "Journal of Vacuum Science and Technology A: Vacuum, Surfaces and Films",

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Skinner, CH, Blanchard, W, Kamperschroer, J, LaMarche, P, Mueller, D, Nagy, A, Scott, S, Ascione, G, Amarescu, E, Camp, R, Casey, M, Collins, J, Cropper, M, Gentile, C, Gibson, M, Hosea, J, Kalish, M, Langford, J, Langish, S, Mika, R, Owens, DK, Pearson, G, Raftopoulos, S, Raucci, R, Stevenson, T, Von Halle, A, Voorhees, D, Walters, T & Winston, J 1996, 'Measurements of tritium retention and removal on the Tokamak Fusion Test Reactor', Journal of Vacuum Science and Technology A: Vacuum, Surfaces and Films, vol. 14, no. 6, pp. 3267-3274. https://doi.org/10.1116/1.580224

TY - JOUR

T1 - Measurements of tritium retention and removal on the Tokamak Fusion Test Reactor

AU - Skinner, C. H.

AU - Blanchard, W.

AU - Kamperschroer, J.

AU - LaMarche, P.

AU - Mueller, D.

AU - Nagy, A.

AU - Scott, S.

AU - Ascione, G.

AU - Amarescu, E.

AU - Camp, R.

AU - Casey, M.

AU - Collins, J.

AU - Cropper, M.

AU - Gentile, C.

AU - Gibson, M.

AU - Hosea, J.

AU - Kalish, M.

AU - Langford, J.

AU - Langish, S.

AU - Mika, R.

AU - Owens, D. K.

AU - Pearson, G.

AU - Raftopoulos, S.

AU - Raucci, R.

AU - Stevenson, T.

AU - Von Halle, A.

AU - Voorhees, D.

AU - Walters, T.

AU - Winston, J.

PY - 1996

Y1 - 1996

N2 - Recent experiments on the Tokamak Fusion Test Reactor have afforded an opportunity to measure the retention of tritium in a graphite limiter that is subject to erosion, codeposition, and high neutron flux. The tritium was injected by both gas puff and neutral beams. The isotopic mix of hydrogenic recycling was measured spectroscopically and the tritium fraction T/(H+D+T) transiently increased to as high as 75%. Some tritium was pumped out during the experimental run and some removed in a subsequent campaign using various clean-up techniques. While the short term retention of tritium was high, various conditioning techniques were successful in removing ≈8000 Ci and restoring the tritium inventory to a level well below the administrative limit.

AB - Recent experiments on the Tokamak Fusion Test Reactor have afforded an opportunity to measure the retention of tritium in a graphite limiter that is subject to erosion, codeposition, and high neutron flux. The tritium was injected by both gas puff and neutral beams. The isotopic mix of hydrogenic recycling was measured spectroscopically and the tritium fraction T/(H+D+T) transiently increased to as high as 75%. Some tritium was pumped out during the experimental run and some removed in a subsequent campaign using various clean-up techniques. While the short term retention of tritium was high, various conditioning techniques were successful in removing ≈8000 Ci and restoring the tritium inventory to a level well below the administrative limit.

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JO - Journal of Vacuum Science and Technology A: Vacuum, Surfaces and Films

JF - Journal of Vacuum Science and Technology A: Vacuum, Surfaces and Films

IS - 6

ER -

Measurements of tritium retention and removal on the Tokamak Fusion Test Reactor

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All Science Journal Classification (ASJC) codes

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