Tungsten coating on JET divertor tiles for erosion/deposition studies

Sari Lehto; Jari Likonen; J.P. Coad; T. Ahlgren; D.E. Hole; M. Mayer; H. Maier; J. Kolehmainen

doi:10.1016/S0920-3796(03)00291-6

Tungsten coating on JET divertor tiles for erosion/deposition studies

Sari Lehto^*
, Jari Likonen
, J.P. Coad
, T. Ahlgren
, D.E. Hole
, M. Mayer
, H. Maier
, J. Kolehmainen

^*Corresponding author for this work

BA4511 Fusion energy

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

36 Citations (Scopus)

Abstract

Six Joint European Torus (JET) divertor tiles were coated with tungsten marker stripes for erosion/deposition studies. The average thickness was 3.4 µm and the film was uniform within 5% across and within 10% along the stripe. Small amounts of impurities C, Fe, Ni and Cr were found and the in-plane stress was 965 MPa. Resistance to high heat loads was tested in the Neutral Beam Test-bed at JET where a coated carbon fibre composite block was exposed to a total of 113 pulses with a maximum peak power density of 15.7 MW m−2 and a maximum surface temperature of 1280 °C. No visible changes as a result of thermal cycling nor sputtering of the film by deuterium could be detected.

Original language	English
Pages (from-to)	241-245
Journal	Fusion Engineering and Design
Volume	66-68
DOIs	https://doi.org/10.1016/S0920-3796(03)00291-6
Publication status	Published - 2003
MoE publication type	A1 Journal article-refereed
Event	22nd Symposium on Fusion Technology - Helsinki, Finland Duration: 9 Sept 2002 → 13 Sept 2002 Conference number: 22

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

SDG 7 Affordable and Clean Energy

Keywords

tungsten coating
plasma
tungsten
erosion
deposition
divertor tiles
divertor
JET
ITER
fusion energy
fusion reactors

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10.1016/S0920-3796(03)00291-6

Cite this

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title = "Tungsten coating on JET divertor tiles for erosion/deposition studies",

abstract = "Six Joint European Torus (JET) divertor tiles were coated with tungsten marker stripes for erosion/deposition studies. The average thickness was 3.4 µm and the film was uniform within 5\% across and within 10\% along the stripe. Small amounts of impurities C, Fe, Ni and Cr were found and the in-plane stress was 965 MPa. Resistance to high heat loads was tested in the Neutral Beam Test-bed at JET where a coated carbon fibre composite block was exposed to a total of 113 pulses with a maximum peak power density of 15.7 MW m−2 and a maximum surface temperature of 1280 °C. No visible changes as a result of thermal cycling nor sputtering of the film by deuterium could be detected.",

keywords = "tungsten coating, plasma, tungsten, erosion, deposition, divertor tiles, divertor, JET, ITER, fusion energy, fusion reactors",

author = "Sari Lehto and Jari Likonen and J.P. Coad and T. Ahlgren and D.E. Hole and M. Mayer and H. Maier and J. Kolehmainen",

year = "2003",

doi = "10.1016/S0920-3796(03)00291-6",

language = "English",

volume = "66-68",

pages = "241--245",

journal = "Fusion Engineering and Design",

issn = "0920-3796",

publisher = "Elsevier",

note = "22nd Symposium on Fusion Technology, SOFTA ; Conference date: 09-09-2002 Through 13-09-2002",

}

TY - JOUR

T1 - Tungsten coating on JET divertor tiles for erosion/deposition studies

AU - Lehto, Sari

AU - Likonen, Jari

AU - Coad, J.P.

AU - Ahlgren, T.

AU - Hole, D.E.

AU - Mayer, M.

AU - Maier, H.

AU - Kolehmainen, J.

N1 - Conference code: 22

PY - 2003

Y1 - 2003

N2 - Six Joint European Torus (JET) divertor tiles were coated with tungsten marker stripes for erosion/deposition studies. The average thickness was 3.4 µm and the film was uniform within 5% across and within 10% along the stripe. Small amounts of impurities C, Fe, Ni and Cr were found and the in-plane stress was 965 MPa. Resistance to high heat loads was tested in the Neutral Beam Test-bed at JET where a coated carbon fibre composite block was exposed to a total of 113 pulses with a maximum peak power density of 15.7 MW m−2 and a maximum surface temperature of 1280 °C. No visible changes as a result of thermal cycling nor sputtering of the film by deuterium could be detected.

AB - Six Joint European Torus (JET) divertor tiles were coated with tungsten marker stripes for erosion/deposition studies. The average thickness was 3.4 µm and the film was uniform within 5% across and within 10% along the stripe. Small amounts of impurities C, Fe, Ni and Cr were found and the in-plane stress was 965 MPa. Resistance to high heat loads was tested in the Neutral Beam Test-bed at JET where a coated carbon fibre composite block was exposed to a total of 113 pulses with a maximum peak power density of 15.7 MW m−2 and a maximum surface temperature of 1280 °C. No visible changes as a result of thermal cycling nor sputtering of the film by deuterium could be detected.

KW - tungsten coating

KW - plasma

KW - tungsten

KW - erosion

KW - deposition

KW - divertor tiles

KW - divertor

KW - JET

KW - ITER

KW - fusion energy

KW - fusion reactors

U2 - 10.1016/S0920-3796(03)00291-6

DO - 10.1016/S0920-3796(03)00291-6

M3 - Article

SN - 0920-3796

VL - 66-68

SP - 241

EP - 245

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

T2 - 22nd Symposium on Fusion Technology

Y2 - 9 September 2002 through 13 September 2002

ER -

Tungsten coating on JET divertor tiles for erosion/deposition studies

Abstract

UN SDGs

Keywords

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