Removal of tritium from TFTR

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

doi:10.13182/fst96-a11963042

Removal of tritium from TFTR

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

PPPL Engineering

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

6 Scopus citations

Abstract

Operation of the Tokamak Fusion Test Reactor (TFTR) with a mixture of deuterium and tritium fueling has permitted the opportunity to measure the retention of tritium in the graphite limiter and other internal hardware. The use of discharge cleaning techniques and venting to remove the tritium was investigated. The tritium was introduced into TFTR by neutral beam injection and by gas puffing. The graphite 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 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)	840-844
Number of pages	5
Journal	Unknown Journal
Volume	30
Issue number	3
DOIs	https://doi.org/10.13182/fst96-a11963042
State	Published - 1996
Event	Proceedings of the 1996 12th Topical Meeting on the Technology of Fusion Energy. Part 2 (of 2) - Reno, NV, USA Duration: Jun 16 1996 → Jun 20 1996

All Science Journal Classification (ASJC) codes

General Engineering

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10.13182/fst96-a11963042

Cite this

@article{40637952e9ba471f99a1a499e43f9a6f,

title = "Removal of tritium from TFTR",

abstract = "Operation of the Tokamak Fusion Test Reactor (TFTR) with a mixture of deuterium and tritium fueling has permitted the opportunity to measure the retention of tritium in the graphite limiter and other internal hardware. The use of discharge cleaning techniques and venting to remove the tritium was investigated. The tritium was introduced into TFTR by neutral beam injection and by gas puffing. The graphite 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 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 A. Nagy and Owens, \{D. K.\} and S. Raftopoulos and Skinner, \{C. H.\}",

year = "1996",

doi = "10.13182/fst96-a11963042",

language = "English (US)",

volume = "30",

pages = "840--844",

journal = "Unknown Journal",

issn = "0011-9164",

publisher = "Elsevier B.V.",

number = "3",

note = "Proceedings of the 1996 12th Topical Meeting on the Technology of Fusion Energy. Part 2 (of 2) ; Conference date: 16-06-1996 Through 20-06-1996",

}

TY - JOUR

T1 - Removal of tritium from TFTR

AU - Mueller, D.

AU - Blanchard, W.

AU - Collins, J.

AU - Hosea, J.

AU - Kamperschroer, J.

AU - Nagy, A.

AU - Owens, D. K.

AU - Raftopoulos, S.

AU - Skinner, C. H.

PY - 1996

Y1 - 1996

N2 - Operation of the Tokamak Fusion Test Reactor (TFTR) with a mixture of deuterium and tritium fueling has permitted the opportunity to measure the retention of tritium in the graphite limiter and other internal hardware. The use of discharge cleaning techniques and venting to remove the tritium was investigated. The tritium was introduced into TFTR by neutral beam injection and by gas puffing. The graphite 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 at the end of 1995 operation to 7.2 kCi at the start of the 1996 experimental program.

AB - Operation of the Tokamak Fusion Test Reactor (TFTR) with a mixture of deuterium and tritium fueling has permitted the opportunity to measure the retention of tritium in the graphite limiter and other internal hardware. The use of discharge cleaning techniques and venting to remove the tritium was investigated. The tritium was introduced into TFTR by neutral beam injection and by gas puffing. The graphite 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 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/0030073883

UR - https://www.scopus.com/pages/publications/0030073883#tab=citedBy

U2 - 10.13182/fst96-a11963042

DO - 10.13182/fst96-a11963042

M3 - Conference article

AN - SCOPUS:0030073883

SN - 0011-9164

VL - 30

SP - 840

EP - 844

JO - Unknown Journal

JF - Unknown Journal

IS - 3

T2 - Proceedings of the 1996 12th Topical Meeting on the Technology of Fusion Energy. Part 2 (of 2)

Y2 - 16 June 1996 through 20 June 1996

ER -

Removal of tritium from TFTR

Abstract

All Science Journal Classification (ASJC) codes

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