R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project

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

Standard

R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project. / Hirai, T.; Maier, H.; Rubel, M.; Mertens, Ph.; Neu, R.; Gauthier, E.; Likonen, J.; Lungu, C.; Maddaluno, G.; Matthews, G.F.; Mitteau, R.; Neubauer, O.; Piazza, G.; Philipps, V.; Riccardi, B.; Ruset, C.; Uytdenhouwen, Inge; Chaouadi, Rachid (Peer reviewer).

In: fusion engineering and design, Vol. 82, No. 15-24, 17.04.2007, p. 1839-1845.

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

Harvard

Hirai, T, Maier, H, Rubel, M, Mertens, P, Neu, R, Gauthier, E, Likonen, J, Lungu, C, Maddaluno, G, Matthews, GF, Mitteau, R, Neubauer, O, Piazza, G, Philipps, V, Riccardi, B, Ruset, C, Uytdenhouwen, I & Chaouadi, R 2007, 'R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project', fusion engineering and design, vol. 82, no. 15-24, pp. 1839-1845. https://doi.org/10.1016/j.fusengdes.2007.02.024

APA

Hirai, T., Maier, H., Rubel, M., Mertens, P., Neu, R., Gauthier, E., Likonen, J., Lungu, C., Maddaluno, G., Matthews, G. F., Mitteau, R., Neubauer, O., Piazza, G., Philipps, V., Riccardi, B., Ruset, C., Uytdenhouwen, I., & Chaouadi, R. (2007). R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project. fusion engineering and design, 82(15-24), 1839-1845. https://doi.org/10.1016/j.fusengdes.2007.02.024

Vancouver

Hirai T, Maier H, Rubel M, Mertens P, Neu R, Gauthier E et al. R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project. fusion engineering and design. 2007 Apr 17;82(15-24):1839-1845. https://doi.org/10.1016/j.fusengdes.2007.02.024

Author

Hirai, T. ; Maier, H. ; Rubel, M. ; Mertens, Ph. ; Neu, R. ; Gauthier, E. ; Likonen, J. ; Lungu, C. ; Maddaluno, G. ; Matthews, G.F. ; Mitteau, R. ; Neubauer, O. ; Piazza, G. ; Philipps, V. ; Riccardi, B. ; Ruset, C. ; Uytdenhouwen, Inge ; Chaouadi, Rachid. / R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project. In: fusion engineering and design. 2007 ; Vol. 82, No. 15-24. pp. 1839-1845.

Bibtex - Download

@article{90e0933fa69b4116a7cdf5959935c710,
title = "R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project",
abstract = "The ITER reference materials have been tested separately in tokamaks, plasma simulators, ion beams and high heat flux test beds. In order to perform a fully integrated material test JET has launched the ITER-like Wall Project with the aim of installing a full metal wall during the next major shutdown. As a result of R&D projects in 2005–2006, bulk tungsten tiles are foreseen at the outer horizontal target and tungsten coating at the other divertor tiles. In some regions of the main chamber, beryllium coated Inconel tiles and bulk beryllium tiles are utilised which include marker tiles as erosion diagnostics. This paper gives an overview of the R&D carried out in the frame of the ITER-like Wall Project on the development of an inertially cooled bulk tungsten tile design and the characterization of tungsten and beryllium coating technologies.",
keywords = "Tungsten, beryllium, CFC, coating, JET, ITER, Plasma facing materials, high heat flux test",
author = "T. Hirai and H. Maier and M. Rubel and Ph. Mertens and R. Neu and E. Gauthier and J. Likonen and C. Lungu and G. Maddaluno and G.F. Matthews and R. Mitteau and O. Neubauer and G. Piazza and V. Philipps and B. Riccardi and C. Ruset and Inge Uytdenhouwen and Rachid Chaouadi",
note = "Score = 10; 24th Symposium on Fusion Technology (SOFT) ; Conference date: 11-09-2006 Through 15-09-2006",
year = "2007",
month = apr,
day = "17",
doi = "10.1016/j.fusengdes.2007.02.024",
language = "English",
volume = "82",
pages = "1839--1845",
journal = "Fusion Engineering & Design",
issn = "0920-3796",
publisher = "Elsevier",
number = "15-24",

}

RIS - Download

TY - JOUR

T1 - R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project

AU - Hirai, T.

AU - Maier, H.

AU - Rubel, M.

AU - Mertens, Ph.

AU - Neu, R.

AU - Gauthier, E.

AU - Likonen, J.

AU - Lungu, C.

AU - Maddaluno, G.

AU - Matthews, G.F.

AU - Mitteau, R.

AU - Neubauer, O.

AU - Piazza, G.

AU - Philipps, V.

AU - Riccardi, B.

AU - Ruset, C.

AU - Uytdenhouwen, Inge

A2 - Chaouadi, Rachid

N1 - Score = 10

PY - 2007/4/17

Y1 - 2007/4/17

N2 - The ITER reference materials have been tested separately in tokamaks, plasma simulators, ion beams and high heat flux test beds. In order to perform a fully integrated material test JET has launched the ITER-like Wall Project with the aim of installing a full metal wall during the next major shutdown. As a result of R&D projects in 2005–2006, bulk tungsten tiles are foreseen at the outer horizontal target and tungsten coating at the other divertor tiles. In some regions of the main chamber, beryllium coated Inconel tiles and bulk beryllium tiles are utilised which include marker tiles as erosion diagnostics. This paper gives an overview of the R&D carried out in the frame of the ITER-like Wall Project on the development of an inertially cooled bulk tungsten tile design and the characterization of tungsten and beryllium coating technologies.

AB - The ITER reference materials have been tested separately in tokamaks, plasma simulators, ion beams and high heat flux test beds. In order to perform a fully integrated material test JET has launched the ITER-like Wall Project with the aim of installing a full metal wall during the next major shutdown. As a result of R&D projects in 2005–2006, bulk tungsten tiles are foreseen at the outer horizontal target and tungsten coating at the other divertor tiles. In some regions of the main chamber, beryllium coated Inconel tiles and bulk beryllium tiles are utilised which include marker tiles as erosion diagnostics. This paper gives an overview of the R&D carried out in the frame of the ITER-like Wall Project on the development of an inertially cooled bulk tungsten tile design and the characterization of tungsten and beryllium coating technologies.

KW - Tungsten

KW - beryllium

KW - CFC

KW - coating

KW - JET

KW - ITER

KW - Plasma facing materials

KW - high heat flux test

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_94554

UR - http://knowledgecentre.sckcen.be/so2/bibref/5533

U2 - 10.1016/j.fusengdes.2007.02.024

DO - 10.1016/j.fusengdes.2007.02.024

M3 - Article

VL - 82

SP - 1839

EP - 1845

JO - Fusion Engineering & Design

JF - Fusion Engineering & Design

SN - 0920-3796

IS - 15-24

T2 - 24th Symposium on Fusion Technology (SOFT)

Y2 - 11 September 2006 through 15 September 2006

ER -

ID: 278931