EU R&amp;D on divertor components

Merola, M.; Dänner, W.; Pick, M.

doi:10.1016/j.fusengdes.2005.06.139

Cited by 31 publications

(14 citation statements)

References 12 publications

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“…This is based on their excellent thermal shock resistance [1,2], absence of melting in comparison with metals and ability to retain the strength up to high temperatures [3,4]. These are desirable properties for the strike point area of the ITER divertor during the start-up phase without tritium [5][6][7] as well as for the divertor of WENDELSTEIN 7-X [8,9].…”

Section: Mechanical and Thermo-physical Characterization Of 3-directimentioning

confidence: 99%

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Mechanical and thermo-physical characterization of three-directional carbon fiber composites for W-7X and ITER

Pintsuk

Compan

Koppitz

et al. 2009

Fusion Engineering and Design

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Carbon fiber composites (CFCs) are the first choice as plasma facing materials for the strike points of divertor targets for future nuclear fusion devices like WENDELSTEIN 7-X and ITER. For the application in these facilities several potential European 3D-CFCs were compared and qualified: 1) four material batches of NB31 produced by Snecma Propulsion Solide (SNECMA); 2) NB41, SNECMA, the upgraded version of NB31; 3) N31, SNECMA, which is densified by chemical vapor infiltration (CVI) instead of a final liquid pitch infiltration characteristic for NB31; 4) a new developmental 3D-CFC produced by DUNLOP.The characterization of the composites is comprised of thermo-physical measurements and tensile tests. The results are correlated to density and microstructure and summarized as follows: 1) NB41 provides the highest thermal conductivity in the ex-pitch direction of ~375 W/m.K at room temperature; 2) all material grades are, due to their heterogeneity, characterized by a relatively large scatter of mechanical properties; 3) the different densification process for N31 in comparison to NB31 has no influence on the material properties; 4) NB41 provides in all 3 directions a comparably high tensile strength with an average in the ex-pitch direction of ~220 MPa; 5) the 3D-

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Section: Mechanical and Thermo-physical Characterization Of 3-directimentioning

confidence: 99%

“…These have to fulfill the occurring manufacturing and operational needs which is nowadays also a matter of numerical simulations [5,10]. Among these materials are several CFCs, for which the characterization results are summarized in [11,12].…”

Section: Mechanical and Thermo-physical Characterization Of 3-directimentioning

confidence: 99%

Mechanical and thermo-physical characterization of three-directional carbon fiber composites for W-7X and ITER

Pintsuk

Compan

Koppitz

et al. 2009

Fusion Engineering and Design

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“…This makes tungsten unsuitable as a structural material if operating below the transition temperature [1]. It has therefore been proposed to join the tungsten armour tile with a material suitable for use as a structural and heat sinking component [6,7]. Copper alloys have been identified as a solution due to its high thermal conductivity amongst other properties [7,8].…”

Section: Introductionmentioning

confidence: 99%

Brazing development and interfacial metallurgy study of tungsten and copper joints with eutectic gold copper brazing alloy

Easton

Zhang

Wood

et al. 2015

Fusion Engineering and Design

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This version is available at https://strathprints.strath.ac.uk/53935/ Strathprints is designed to allow users to access the research output of the University of Strathclyde. Unless otherwise explicitly stated on the manuscript, Copyright © and Moral Rights for the papers on this site are retained by the individual authors and/or other copyright owners. Please check the manuscript for details of any other licences that may have been applied. You may not engage in further distribution of the material for any profitmaking activities or any commercial gain. You may freely distribute both the url (https://strathprints.strath.ac.uk/) and the content of this paper for research or private study, educational, or not-for-profit purposes without prior permission or charge.Any correspondence concerning this service should be sent to the Strathprints administrator: strathprints@strath.ac.ukThe Strathprints institutional repository (https://strathprints.strath.ac.uk) is a digital archive of University of Strathclyde research outputs. It has been developed to disseminate open access research outputs, expose data about those outputs, and enable the management and persistent access to Strathclyde's intellectual output. Current proposals for the divertor component of a thermonuclear fusion reactor include tungsten and copper as potentially suitable materials. This paper presents the procedures developed for the successful brazing of tungsten to oxygen free high conductivity (OFHC) copper using a fusion appropriate gold based brazing alloy, Orobraze 890 (Au80Cu20). The objectives were to develop preparation techniques and brazing procedures in order to produce a repeatable, defect free butt joint for tungsten to copper. Multiple brazing methods were utilised and brazing parameters altered to achieve the best joint possible. Successful and unsuccessful brazed specimens were sectioned and analysed using optical and scanning electron microscopy, EDX analysis and ultrasonic evaluation. It has been determined that brazing with Au80Cu20 has the potential to be a suitable joining method for a tungsten to copper joint. Brazing Development and Interfacial Metallurgy Study of Tungsten and Copper Joints with Eutectic Gold Copper Brazing Alloy

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“…PFC which will be installed in the ITER Divertor, require a heat flux removal capability in the range 5-10 MW/m 2 in thermal steady-state conditions and up to 20 MW/m 2 in transients. Well in advance of the assumed start of the procurement, each ITER party should first demonstrate its technical capability to carry out the procurement with the required quality, and in an efficient and timely manner [1]. This is achieved via the successful manufacturing and testing of medium-size "Qualification Prototypes" (QP) made of three HHF units.…”

Section: Introductionmentioning

confidence: 99%

Infrared thermography inspection of the ITER vertical target qualification prototypes manufactured by European industry using SATIR

Durocher¹,

Escourbiac²,

Richou³

et al. 2009

Fusion Engineering and Design

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EU R&D on divertor components

Cited by 31 publications

References 12 publications

Mechanical and thermo-physical characterization of three-directional carbon fiber composites for W-7X and ITER

Mechanical and thermo-physical characterization of three-directional carbon fiber composites for W-7X and ITER

Brazing development and interfacial metallurgy study of tungsten and copper joints with eutectic gold copper brazing alloy

Infrared thermography inspection of the ITER vertical target qualification prototypes manufactured by European industry using SATIR

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