Fusion technology engineering R&D at JET

S. Ciattaglia, B. Benoit, P. Coad, A. Coletti, R. Forrest, J. Fricconneau, E. Gautier, C. Grisolia, R. Lässer, Jari Likonen, M. Mayer, T. Pinna, F. Scaffidi-Argentina

Research output: Chapter in Book/Report/Conference proceedingConference abstract in proceedingsScientific

Abstract

Research activities that can provide adequate contributions or solutions to technological issues of importance for both JET and ITER are carried out at Culham and in the European national laboratories. They are closely related to the EFDA Technology Workprogramme. This programme of Fusion Technology at JET (FT) covers a wide range of research areas such as tritium in the tokamak, tritium processes and waste management, plasma facing components, other fusion engineering aspects and safety. This paper presents the status and the programme of those fusion technology activities at JET not directly related to tritium. The characterisation of first wall material using various surface analytical techniques (SIMS, TOF-ERDA, RBS, NRA, IBA) is carried out on tiles removed from JET. The results are analysed by taking into account the actual integrated ion flux on the plasma exposed surfaces. To investigate the erosion properties of tungsten, a poloidal set of 6 carbon tiles has been covered with tungsten layers and were installed in the JET machine during the 2001 shutdown. A programme using long-term samples (LTS) for erosion rate measurements and sticking monitors to determine sticking coefficients of hydrocarbon radicals is in progress. A few Mark II Divertor tiles will be tested in the Neutral Beam (NB) test bed facility, simulating different JET plasma heat loads, in order to validate a model for plasma facing components behaviour and the mechanism of first wall material transport. Optic fibres under qualification for ITER use will be tested on JET as well as an in-vessel viewing system based on laser technology in order to increase the quality and the completeness of the images. Data of the operating experience of the major JET systems as well data on operating experience with Remote Handling facilities during the JET shutdowns are collected and elaborated to support the ITER design with an improved failure rate data base and operating experience. Nuclear activation and shutdown dose rate calculation models are benchmarked on JET and some models have been significantly improved.
Original languageEnglish
Title of host publication22nd Symposium on Fusion Technology
Subtitle of host publicationBook of Abstracts
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages90-90
ISBN (Electronic)951-38-5731-X
ISBN (Print)951-38-5730-1
Publication statusPublished - 2002
Event22nd Symposium on Fusion Technology - Helsinki, Finland
Duration: 9 Sep 200213 Sep 2002
Conference number: 22

Publication series

SeriesVTT Symposium
Number220
ISSN0357-9387

Conference

Conference22nd Symposium on Fusion Technology
Abbreviated titleSOFTA
CountryFinland
CityHelsinki
Period9/09/0213/09/02

Fingerprint

shutdowns
tiles
tritium
fusion
engineering
erosion
tungsten
remote handling
waste management
test stands
neutral beams
qualifications
data bases
completeness
secondary ion mass spectrometry
vessels
monitors
fiber optics
safety
hydrocarbons

Cite this

Ciattaglia, S., Benoit, B., Coad, P., Coletti, A., Forrest, R., Fricconneau, J., ... Scaffidi-Argentina, F. (2002). Fusion technology engineering R&D at JET. In 22nd Symposium on Fusion Technology: Book of Abstracts (pp. 90-90). [B-49] Espoo: VTT Technical Research Centre of Finland. VTT Symposium, No. 220
Ciattaglia, S. ; Benoit, B. ; Coad, P. ; Coletti, A. ; Forrest, R. ; Fricconneau, J. ; Gautier, E. ; Grisolia, C. ; Lässer, R. ; Likonen, Jari ; Mayer, M. ; Pinna, T. ; Scaffidi-Argentina, F. / Fusion technology engineering R&D at JET. 22nd Symposium on Fusion Technology: Book of Abstracts. Espoo : VTT Technical Research Centre of Finland, 2002. pp. 90-90 (VTT Symposium; No. 220).
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abstract = "Research activities that can provide adequate contributions or solutions to technological issues of importance for both JET and ITER are carried out at Culham and in the European national laboratories. They are closely related to the EFDA Technology Workprogramme. This programme of Fusion Technology at JET (FT) covers a wide range of research areas such as tritium in the tokamak, tritium processes and waste management, plasma facing components, other fusion engineering aspects and safety. This paper presents the status and the programme of those fusion technology activities at JET not directly related to tritium. The characterisation of first wall material using various surface analytical techniques (SIMS, TOF-ERDA, RBS, NRA, IBA) is carried out on tiles removed from JET. The results are analysed by taking into account the actual integrated ion flux on the plasma exposed surfaces. To investigate the erosion properties of tungsten, a poloidal set of 6 carbon tiles has been covered with tungsten layers and were installed in the JET machine during the 2001 shutdown. A programme using long-term samples (LTS) for erosion rate measurements and sticking monitors to determine sticking coefficients of hydrocarbon radicals is in progress. A few Mark II Divertor tiles will be tested in the Neutral Beam (NB) test bed facility, simulating different JET plasma heat loads, in order to validate a model for plasma facing components behaviour and the mechanism of first wall material transport. Optic fibres under qualification for ITER use will be tested on JET as well as an in-vessel viewing system based on laser technology in order to increase the quality and the completeness of the images. Data of the operating experience of the major JET systems as well data on operating experience with Remote Handling facilities during the JET shutdowns are collected and elaborated to support the ITER design with an improved failure rate data base and operating experience. Nuclear activation and shutdown dose rate calculation models are benchmarked on JET and some models have been significantly improved.",
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Ciattaglia, S, Benoit, B, Coad, P, Coletti, A, Forrest, R, Fricconneau, J, Gautier, E, Grisolia, C, Lässer, R, Likonen, J, Mayer, M, Pinna, T & Scaffidi-Argentina, F 2002, Fusion technology engineering R&D at JET. in 22nd Symposium on Fusion Technology: Book of Abstracts., B-49, VTT Technical Research Centre of Finland, Espoo, VTT Symposium, no. 220, pp. 90-90, 22nd Symposium on Fusion Technology, Helsinki, Finland, 9/09/02.

Fusion technology engineering R&D at JET. / Ciattaglia, S.; Benoit, B.; Coad, P.; Coletti, A.; Forrest, R.; Fricconneau, J.; Gautier, E.; Grisolia, C.; Lässer, R.; Likonen, Jari; Mayer, M.; Pinna, T.; Scaffidi-Argentina, F.

22nd Symposium on Fusion Technology: Book of Abstracts. Espoo : VTT Technical Research Centre of Finland, 2002. p. 90-90 B-49 (VTT Symposium; No. 220).

Research output: Chapter in Book/Report/Conference proceedingConference abstract in proceedingsScientific

TY - CHAP

T1 - Fusion technology engineering R&D at JET

AU - Ciattaglia, S.

AU - Benoit, B.

AU - Coad, P.

AU - Coletti, A.

AU - Forrest, R.

AU - Fricconneau, J.

AU - Gautier, E.

AU - Grisolia, C.

AU - Lässer, R.

AU - Likonen, Jari

AU - Mayer, M.

AU - Pinna, T.

AU - Scaffidi-Argentina, F.

PY - 2002

Y1 - 2002

N2 - Research activities that can provide adequate contributions or solutions to technological issues of importance for both JET and ITER are carried out at Culham and in the European national laboratories. They are closely related to the EFDA Technology Workprogramme. This programme of Fusion Technology at JET (FT) covers a wide range of research areas such as tritium in the tokamak, tritium processes and waste management, plasma facing components, other fusion engineering aspects and safety. This paper presents the status and the programme of those fusion technology activities at JET not directly related to tritium. The characterisation of first wall material using various surface analytical techniques (SIMS, TOF-ERDA, RBS, NRA, IBA) is carried out on tiles removed from JET. The results are analysed by taking into account the actual integrated ion flux on the plasma exposed surfaces. To investigate the erosion properties of tungsten, a poloidal set of 6 carbon tiles has been covered with tungsten layers and were installed in the JET machine during the 2001 shutdown. A programme using long-term samples (LTS) for erosion rate measurements and sticking monitors to determine sticking coefficients of hydrocarbon radicals is in progress. A few Mark II Divertor tiles will be tested in the Neutral Beam (NB) test bed facility, simulating different JET plasma heat loads, in order to validate a model for plasma facing components behaviour and the mechanism of first wall material transport. Optic fibres under qualification for ITER use will be tested on JET as well as an in-vessel viewing system based on laser technology in order to increase the quality and the completeness of the images. Data of the operating experience of the major JET systems as well data on operating experience with Remote Handling facilities during the JET shutdowns are collected and elaborated to support the ITER design with an improved failure rate data base and operating experience. Nuclear activation and shutdown dose rate calculation models are benchmarked on JET and some models have been significantly improved.

AB - Research activities that can provide adequate contributions or solutions to technological issues of importance for both JET and ITER are carried out at Culham and in the European national laboratories. They are closely related to the EFDA Technology Workprogramme. This programme of Fusion Technology at JET (FT) covers a wide range of research areas such as tritium in the tokamak, tritium processes and waste management, plasma facing components, other fusion engineering aspects and safety. This paper presents the status and the programme of those fusion technology activities at JET not directly related to tritium. The characterisation of first wall material using various surface analytical techniques (SIMS, TOF-ERDA, RBS, NRA, IBA) is carried out on tiles removed from JET. The results are analysed by taking into account the actual integrated ion flux on the plasma exposed surfaces. To investigate the erosion properties of tungsten, a poloidal set of 6 carbon tiles has been covered with tungsten layers and were installed in the JET machine during the 2001 shutdown. A programme using long-term samples (LTS) for erosion rate measurements and sticking monitors to determine sticking coefficients of hydrocarbon radicals is in progress. A few Mark II Divertor tiles will be tested in the Neutral Beam (NB) test bed facility, simulating different JET plasma heat loads, in order to validate a model for plasma facing components behaviour and the mechanism of first wall material transport. Optic fibres under qualification for ITER use will be tested on JET as well as an in-vessel viewing system based on laser technology in order to increase the quality and the completeness of the images. Data of the operating experience of the major JET systems as well data on operating experience with Remote Handling facilities during the JET shutdowns are collected and elaborated to support the ITER design with an improved failure rate data base and operating experience. Nuclear activation and shutdown dose rate calculation models are benchmarked on JET and some models have been significantly improved.

M3 - Conference abstract in proceedings

SN - 951-38-5730-1

T3 - VTT Symposium

SP - 90

EP - 90

BT - 22nd Symposium on Fusion Technology

PB - VTT Technical Research Centre of Finland

CY - Espoo

ER -

Ciattaglia S, Benoit B, Coad P, Coletti A, Forrest R, Fricconneau J et al. Fusion technology engineering R&D at JET. In 22nd Symposium on Fusion Technology: Book of Abstracts. Espoo: VTT Technical Research Centre of Finland. 2002. p. 90-90. B-49. (VTT Symposium; No. 220).