Tritium reduction and control in the vacuum vessel during TFTR outage and decommissioning

W. Blanchard; R. Camp; H. Carnevale; M. Casey; J. Collins; C. A. Gentile; M. Gibson; J. C. Hosea; M. Kalish; J. Langford; S. Langish; D. Miller; A. Nagy; G. G. Pearson; R. Raucci; al et al

Tritium reduction and control in the vacuum vessel during TFTR outage and decommissioning

W. Blanchard, R. Camp, H. Carnevale, M. Casey, J. Collins, C. A. Gentile, M. Gibson, J. C. Hosea, M. Kalish, J. Langford, S. Langish, D. Miller, A. Nagy, G. G. Pearson, R. Raucci, al et al

PPPL Engineering

Research output: Contribution to conference › Paper › peer-review

1 Scopus citations

Abstract

In 1996, TFTR underwent an extended outage during which large port covers were removed from the vacuum vessel in order to complete upgrades to the tokamak. Following a venting of the torus, a three tier system was developed for the outage in order to reduce and control the free tritium in the vacuum vessel so as to minimize the exposure to personnel during port cover removal and reinstallation. Several systems were implemented that successfully reduced and controlled the free tritium in TFTR and were instrumental in maintaining As Low As Reasonably Achievable (ALARA) exposures to tritium. The same systems are again being used during the safe shutdown and decommissioning of TFTR which commenced in April of 1997.

Original language	English (US)
Pages	297-300
Number of pages	4
State	Published - 1998
Event	Proceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2) - San Diego, CA, USA Duration: Oct 6 1997 → Oct 10 1997

Other

Other	Proceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2)
City	San Diego, CA, USA
Period	10/6/97 → 10/10/97

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Nuclear Energy and Engineering

Cite this

Blanchard, W., Camp, R., Carnevale, H., Casey, M., Collins, J., Gentile, C. A., Gibson, M., Hosea, J. C., Kalish, M., Langford, J., Langish, S., Miller, D., Nagy, A., Pearson, G. G., Raucci, R., & et al, A. (1998). Tritium reduction and control in the vacuum vessel during TFTR outage and decommissioning. 297-300. Paper presented at Proceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2), San Diego, CA, USA.

@conference{487947d17a7545c4b9c93dad8745f281,

title = "Tritium reduction and control in the vacuum vessel during TFTR outage and decommissioning",

abstract = "In 1996, TFTR underwent an extended outage during which large port covers were removed from the vacuum vessel in order to complete upgrades to the tokamak. Following a venting of the torus, a three tier system was developed for the outage in order to reduce and control the free tritium in the vacuum vessel so as to minimize the exposure to personnel during port cover removal and reinstallation. Several systems were implemented that successfully reduced and controlled the free tritium in TFTR and were instrumental in maintaining As Low As Reasonably Achievable (ALARA) exposures to tritium. The same systems are again being used during the safe shutdown and decommissioning of TFTR which commenced in April of 1997.",

author = "W. Blanchard and R. Camp and H. Carnevale and M. Casey and J. Collins and Gentile, \{C. A.\} and M. Gibson and Hosea, \{J. C.\} and M. Kalish and J. Langford and S. Langish and D. Miller and A. Nagy and Pearson, \{G. G.\} and R. Raucci and \{et al\}, al",

year = "1998",

language = "English (US)",

pages = "297--300",

note = "Proceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2) ; Conference date: 06-10-1997 Through 10-10-1997",

}

Blanchard, W, Camp, R, Carnevale, H, Casey, M, Collins, J, Gentile, CA, Gibson, M, Hosea, JC, Kalish, M, Langford, J, Langish, S, Miller, D, Nagy, A, Pearson, GG, Raucci, R & et al, A 1998, 'Tritium reduction and control in the vacuum vessel during TFTR outage and decommissioning', Paper presented at Proceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2), San Diego, CA, USA, 10/6/97 - 10/10/97 pp. 297-300.

TY - CONF

T1 - Tritium reduction and control in the vacuum vessel during TFTR outage and decommissioning

AU - Blanchard, W.

AU - Camp, R.

AU - Carnevale, H.

AU - Casey, M.

AU - Collins, J.

AU - Gentile, C. A.

AU - Gibson, M.

AU - Hosea, J. C.

AU - Kalish, M.

AU - Langford, J.

AU - Langish, S.

AU - Miller, D.

AU - Nagy, A.

AU - Pearson, G. G.

AU - Raucci, R.

AU - et al, al

PY - 1998

Y1 - 1998

N2 - In 1996, TFTR underwent an extended outage during which large port covers were removed from the vacuum vessel in order to complete upgrades to the tokamak. Following a venting of the torus, a three tier system was developed for the outage in order to reduce and control the free tritium in the vacuum vessel so as to minimize the exposure to personnel during port cover removal and reinstallation. Several systems were implemented that successfully reduced and controlled the free tritium in TFTR and were instrumental in maintaining As Low As Reasonably Achievable (ALARA) exposures to tritium. The same systems are again being used during the safe shutdown and decommissioning of TFTR which commenced in April of 1997.

AB - In 1996, TFTR underwent an extended outage during which large port covers were removed from the vacuum vessel in order to complete upgrades to the tokamak. Following a venting of the torus, a three tier system was developed for the outage in order to reduce and control the free tritium in the vacuum vessel so as to minimize the exposure to personnel during port cover removal and reinstallation. Several systems were implemented that successfully reduced and controlled the free tritium in TFTR and were instrumental in maintaining As Low As Reasonably Achievable (ALARA) exposures to tritium. The same systems are again being used during the safe shutdown and decommissioning of TFTR which commenced in April of 1997.

UR - https://www.scopus.com/pages/publications/0031619640

UR - https://www.scopus.com/inward/citedby.url?scp=0031619640&partnerID=8YFLogxK

M3 - Paper

AN - SCOPUS:0031619640

SP - 297

EP - 300

T2 - Proceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2)

Y2 - 6 October 1997 through 10 October 1997

ER -

Tritium reduction and control in the vacuum vessel during TFTR outage and decommissioning

Abstract

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All Science Journal Classification (ASJC) codes

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