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(97)80162-6

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 › Article › peer-review

2 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(97)80162-6
State	Published - Feb 11 1997

All Science Journal Classification (ASJC) codes

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

Keywords

Erosion and particle deposition
Fusion
Technology
TFTR
Tokamak
Tritium inventory and economy

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10.1016/s0022-3115(97)80162-6

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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.",

keywords = "Erosion and particle deposition, Fusion, Technology, TFTR, Tokamak, Tritium inventory and economy",

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 = "11",

doi = "10.1016/s0022-3115(97)80162-6",

language = "English (US)",

volume = "241-243",

pages = "897--901",

journal = "Journal of Nuclear Materials",

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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 - 1997/2/11

Y1 - 1997/2/11

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.

KW - Erosion and particle deposition

KW - Fusion

KW - Technology

KW - TFTR

KW - Tokamak

KW - Tritium inventory and economy

UR - https://www.scopus.com/pages/publications/85088224957

UR - https://www.scopus.com/inward/citedby.url?scp=85088224957&partnerID=8YFLogxK

U2 - 10.1016/s0022-3115(97)80162-6

DO - 10.1016/s0022-3115(97)80162-6

M3 - Article

AN - SCOPUS:85088224957

SN - 0022-3115

VL - 241-243

SP - 897

EP - 901

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

ER -

Tritium removal from TFTR

Abstract

All Science Journal Classification (ASJC) codes

Keywords

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