Tritium removal from TFTR

D. Mueller; W. Blanchard; J. Collins; J. Hosea; J. Kamperschroer; P. H. LaMarche; A. Nagy; D. K. Owens; C. H. Skinner

doi:10.1016/S0022-3115(96)00628-9

Tritium removal from TFTR

D. Mueller
, W. Blanchard
, J. Collins
, J. Hosea
, J. Kamperschroer
, P. H. LaMarche
, A. Nagy
, D. K. Owens
, C. H. Skinner

PPPL Engineering

Research output: Contribution to journal › Conference article › peer-review

52 Scopus citations

Abstract

Continued operation of the tokamak fusion test reactor (TFFR) with a mixture of deuterium and tritium fueling has permitted the opportunity to measure the retention of tritium in the graphite limiter and to investigate the use of discharge cleaning techniques and venting to remove the tritium. The tritium was introduced into TFTR by neutral beam injection and by gas puffing. The limiter is subject to erosion and codeposition. While short term retention was high, the retention averaged over the 1993-1995 D-T campaign was 52±15%. The tritium removal techniques resulted in lowering the in-vessel inventory from 16.4 kCi (1 Ci = 2.076×10¹⁹ tritium atoms and 10 kCi = 1.04 g) at the end of 1995 operation to 7.2 kCi at the start of the 1996 experimental program.

Original language	English (US)
Pages (from-to)	897-901
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	241-243
DOIs	https://doi.org/10.1016/S0022-3115(96)00628-9
State	Published - Feb 2 1997
Event	Proceedings of the 1996 12th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices - Saint-Raphael, Fr Duration: May 20 1996 → May 24 1996

All Science Journal Classification (ASJC) codes

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

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10.1016/S0022-3115(96)00628-9

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@article{bed5ce21f403416e88db2afdf88c7598,

title = "Tritium removal from TFTR",

abstract = "Continued operation of the tokamak fusion test reactor (TFFR) with a mixture of deuterium and tritium fueling has permitted the opportunity to measure the retention of tritium in the graphite limiter and to investigate the use of discharge cleaning techniques and venting to remove the tritium. The tritium was introduced into TFTR by neutral beam injection and by gas puffing. The limiter is subject to erosion and codeposition. While short term retention was high, the retention averaged over the 1993-1995 D-T campaign was 52±15\%. The tritium removal techniques resulted in lowering the in-vessel inventory from 16.4 kCi (1 Ci = 2.076×1019 tritium atoms and 10 kCi = 1.04 g) at the end of 1995 operation to 7.2 kCi at the start of the 1996 experimental program.",

author = "D. Mueller and W. Blanchard and J. Collins and J. Hosea and J. Kamperschroer and LaMarche, \{P. H.\} and A. Nagy and Owens, \{D. K.\} and Skinner, \{C. H.\}",

year = "1997",

month = feb,

day = "2",

doi = "10.1016/S0022-3115(96)00628-9",

language = "English (US)",

volume = "241-243",

pages = "897--901",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

note = "Proceedings of the 1996 12th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices ; Conference date: 20-05-1996 Through 24-05-1996",

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TY - JOUR

T1 - Tritium removal from TFTR

AU - Mueller, D.

AU - Blanchard, W.

AU - Collins, J.

AU - Hosea, J.

AU - Kamperschroer, J.

AU - LaMarche, P. H.

AU - Nagy, A.

AU - Owens, D. K.

AU - Skinner, C. H.

PY - 1997/2/2

Y1 - 1997/2/2

N2 - Continued operation of the tokamak fusion test reactor (TFFR) with a mixture of deuterium and tritium fueling has permitted the opportunity to measure the retention of tritium in the graphite limiter and to investigate the use of discharge cleaning techniques and venting to remove the tritium. The tritium was introduced into TFTR by neutral beam injection and by gas puffing. The limiter is subject to erosion and codeposition. While short term retention was high, the retention averaged over the 1993-1995 D-T campaign was 52±15%. The tritium removal techniques resulted in lowering the in-vessel inventory from 16.4 kCi (1 Ci = 2.076×1019 tritium atoms and 10 kCi = 1.04 g) at the end of 1995 operation to 7.2 kCi at the start of the 1996 experimental program.

AB - Continued operation of the tokamak fusion test reactor (TFFR) with a mixture of deuterium and tritium fueling has permitted the opportunity to measure the retention of tritium in the graphite limiter and to investigate the use of discharge cleaning techniques and venting to remove the tritium. The tritium was introduced into TFTR by neutral beam injection and by gas puffing. The limiter is subject to erosion and codeposition. While short term retention was high, the retention averaged over the 1993-1995 D-T campaign was 52±15%. The tritium removal techniques resulted in lowering the in-vessel inventory from 16.4 kCi (1 Ci = 2.076×1019 tritium atoms and 10 kCi = 1.04 g) at the end of 1995 operation to 7.2 kCi at the start of the 1996 experimental program.

UR - https://www.scopus.com/pages/publications/0031546578

UR - https://www.scopus.com/pages/publications/0031546578#tab=citedBy

U2 - 10.1016/S0022-3115(96)00628-9

DO - 10.1016/S0022-3115(96)00628-9

M3 - Conference article

AN - SCOPUS:0031546578

SN - 0022-3115

VL - 241-243

SP - 897

EP - 901

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

T2 - Proceedings of the 1996 12th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices

Y2 - 20 May 1996 through 24 May 1996

ER -

Tritium removal from TFTR

Abstract

All Science Journal Classification (ASJC) codes

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