Methods to determine the joint strength of C/C to copper joints

Schedler, B.; Huber, T.; Eidenberger, Elisabeth; Scheu, Christina; Pippan, Reinhard; Clemens, Helmut

doi:10.1016/j.fusengdes.2007.04.037

Cited by 12 publications

(6 citation statements)

References 10 publications

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“…For those parameters damage is governed by the low value of G c . That emphasizes the need for bond characterisation, which was investigated in [13] and still is a matter of ongoing research [17]. Using previous tensile and shear bond test results [6][13] to identify the parameters, the following set of parameters was identified at room temperature: σ c = 43 MPa, G I c =1900 J.m -2 , G II c =3000 J.m -2 .…”

Section: Crack Initiation and Propagationmentioning

confidence: 99%

CFC/Cu bond damage in actively cooled plasma facing components

et al. 2007

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Carbon fibre composite (CFC) armours have been successfully used for actively cooled plasma facing components (PFCs) of the Tore Supra (TS) tokamak. They were also selected for the divertor of the stellarator W7-X under construction and for the vertical target of the ITER divertor.In TS and W7-X a flat tile design for heat fluxes of 10 MW/m 2 has been chosen. To predict the lifetime of such PFCs, it is necessary to analyse the damage mechanisms and to model the damage propagation when the component is exposed to thermal cycling loads. Work has been performed to identify a constitutive law for the CFC and parameters to model crack propagation from the edge singularity. The aim is to predict damage rates and to propose geometric or material improvements to increase the strength and the lifetime of the interfacial bond.For ITER a tube-in-tile concept (monoblock), designed to sustain heat fluxes up to 20 MW/m 2 , has been developed. The optimisation of the CFC/Cu bond, proposed for flat tiles, could be adopted for the monoblock concept.

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Section: Crack Initiation and Propagationmentioning

confidence: 99%

CFC/Cu bond damage in actively cooled plasma facing components

et al. 2007

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“…L-shaped tiles have a 45° inclination of the carbon fibre planes with respect to the bonding interface. HHF test results performed on GLADIS validated this concept [7]. The casting of the 3 mm thick AMC ® copper interlayer of the reference design will be used for the serial production of the L-shaped tiles.…”

Section: Bond Of the Tiles To The Cooling Structurementioning

confidence: 75%

“…An improvement was achieved by performing this process in presence of silicon in addition. This improvement was demonstrated by a push-test in the shear plane introduced by Plansee SE [7,8]. The samples showed a measured value of ~ 30 MPa and ~ 60 MPa without and with silicon, respectively.…”

Section: Bond Of the Tiles To The Cooling Structurementioning

confidence: 99%

Fabrication and testing of W7-X pre-series target elements

et al. 2007

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The assembly of the highly-loaded target plates of the WENDELSTEIN 7-X (W7-X) divertor requires the fabrication of 890 target elements. The plasma facing material is made of CFC NB31 flat tiles bonded to CuCrZr copper alloy water-cooled heat sink. The elements are designed to remove a stationary heat flux and power up to 10 MW/m 2 and 100 kW, respectively. Before launching the serial fabrication, pre-series activities aimed at qualifying the design, the manufacturing route and the nondestructive examinations. High heat flux tests performed on full-scale pre-series target elements resulted in an improvement of the design of the bond between tiles and heat sink to reduce the stresses during operation. The consequence is the fabrication of additional pre-series target elements to be tested in the high heat flux facility GLADIS. Non-destructive examinations of this bond based on thermography methods are developed to define the acceptance criteria suitable to the serial fabrication.

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“…Indeed, in the CFC the tensile state in the X direction, measured in the as-brazed specimen, is turned into compressive, remaining well below the compressive strength of NB31 along this direction. Schedler et al [12] showed that the CFC-Cu joint strength is weakened after treatments such as quenching and thermal fatigue, due to the formation of microcracks which reduce the integral capability of the joint to transfer mechanical loads. The observed residual stress relaxation could be ascribed to this phenomenon as well.…”

Section: Resultsmentioning

confidence: 99%

Neutron diffraction measurement of residual stresses in CFC/Cu/CuCrZr joints for nuclear fusion technology

Fiori

Calbucci

Casalegno

et al. 2008

J. Phys.: Condens. Matter

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Methods to determine the joint strength of C/C to copper joints

Cited by 12 publications

References 10 publications

CFC/Cu bond damage in actively cooled plasma facing components

CFC/Cu bond damage in actively cooled plasma facing components

Fabrication and testing of W7-X pre-series target elements

Neutron diffraction measurement of residual stresses in CFC/Cu/CuCrZr joints for nuclear fusion technology

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