Erosion and deposition on JET divertor and limiter tiles during the experimental campaigns 2005-2009

S. Krat; J.P. Coad; Y. Gasparyan; Antti Hakola; Jari Likonen; M. Mayer; A. Pisarev; A. Widdowson; JET-EFDA contributors

doi:10.1016/j.jnucmat.2013.01.158

Erosion and deposition on JET divertor and limiter tiles during the experimental campaigns 2005-2009

S. Krat (Corresponding Author), J.P. Coad, Y. Gasparyan, Antti Hakola, Jari Likonen, M. Mayer, A. Pisarev, A. Widdowson, JET-EFDA contributors

Research output: Contribution to journal › Article › Scientific › peer-review

18 Citations (Scopus)

Abstract

Erosion from and deposition on JET divertor tiles used during the 2007–2009 campaign and on inner wall guard limiter (IWGL) tiles used during 2005–2009 are studied. The tungsten coating on the divertor tiles was mostly intact with the largest erosion ∼30% in a small local area. Locally high erosion areas were observed on the load bearing divertor tile 5 and on the horizontal surface of the divertor tile 8. The IWGL tiles show a complicated distribution of erosion and deposition areas. The total amount of carbon deposited on the all IWGL tiles during the campaign 2005–2009 is estimated to be 65 g. The density of carbon deposits is estimated to be 0.67–0.83 g/cm³.

Original language	English
Pages (from-to)	S742-S745
Journal	Journal of Nuclear Materials
Volume	438
Issue number	Supplement
DOIs	https://doi.org/10.1016/j.jnucmat.2013.01.158
Publication status	Published - 2013
MoE publication type	A1 Journal article-refereed
Event	20th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices - Aachen, Aachen, Germany Duration: 21 May 2012 → 25 May 2012

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title = "Erosion and deposition on JET divertor and limiter tiles during the experimental campaigns 2005-2009",

abstract = "Erosion from and deposition on JET divertor tiles used during the 2007–2009 campaign and on inner wall guard limiter (IWGL) tiles used during 2005–2009 are studied. The tungsten coating on the divertor tiles was mostly intact with the largest erosion ∼30% in a small local area. Locally high erosion areas were observed on the load bearing divertor tile 5 and on the horizontal surface of the divertor tile 8. The IWGL tiles show a complicated distribution of erosion and deposition areas. The total amount of carbon deposited on the all IWGL tiles during the campaign 2005–2009 is estimated to be 65 g. The density of carbon deposits is estimated to be 0.67–0.83 g/cm3.",

author = "S. Krat and J.P. Coad and Y. Gasparyan and Antti Hakola and Jari Likonen and M. Mayer and A. Pisarev and A. Widdowson and {JET-EFDA contributors}",

year = "2013",

doi = "10.1016/j.jnucmat.2013.01.158",

language = "English",

volume = "438",

pages = "S742--S745",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

number = "Supplement",

note = "20th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices, PSI-20 ; Conference date: 21-05-2012 Through 25-05-2012",

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TY - JOUR

T1 - Erosion and deposition on JET divertor and limiter tiles during the experimental campaigns 2005-2009

AU - Krat, S.

AU - Coad, J.P.

AU - Gasparyan, Y.

AU - Hakola, Antti

AU - Likonen, Jari

AU - Mayer, M.

AU - Pisarev, A.

AU - Widdowson, A.

AU - JET-EFDA contributors

PY - 2013

Y1 - 2013

N2 - Erosion from and deposition on JET divertor tiles used during the 2007–2009 campaign and on inner wall guard limiter (IWGL) tiles used during 2005–2009 are studied. The tungsten coating on the divertor tiles was mostly intact with the largest erosion ∼30% in a small local area. Locally high erosion areas were observed on the load bearing divertor tile 5 and on the horizontal surface of the divertor tile 8. The IWGL tiles show a complicated distribution of erosion and deposition areas. The total amount of carbon deposited on the all IWGL tiles during the campaign 2005–2009 is estimated to be 65 g. The density of carbon deposits is estimated to be 0.67–0.83 g/cm3.

AB - Erosion from and deposition on JET divertor tiles used during the 2007–2009 campaign and on inner wall guard limiter (IWGL) tiles used during 2005–2009 are studied. The tungsten coating on the divertor tiles was mostly intact with the largest erosion ∼30% in a small local area. Locally high erosion areas were observed on the load bearing divertor tile 5 and on the horizontal surface of the divertor tile 8. The IWGL tiles show a complicated distribution of erosion and deposition areas. The total amount of carbon deposited on the all IWGL tiles during the campaign 2005–2009 is estimated to be 65 g. The density of carbon deposits is estimated to be 0.67–0.83 g/cm3.

U2 - 10.1016/j.jnucmat.2013.01.158

DO - 10.1016/j.jnucmat.2013.01.158

M3 - Article

SN - 0022-3115

VL - 438

SP - S742-S745

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - Supplement

T2 - 20th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices

Y2 - 21 May 2012 through 25 May 2012

ER -

Erosion and deposition on JET divertor and limiter tiles during the experimental campaigns 2005-2009

Abstract

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