Acceptance criteria for the ITER divertor vertical target

Fouquet, S.; Schlösser, J.; Merola, M.; Durocher, A.; Escourbiac, F.; Grosman, A.; Missirlian, M.; Portafaix, C.

doi:10.1016/j.fusengdes.2005.06.363

Cited by 16 publications

(7 citation statements)

References 17 publications

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“…In the VTQP, the acceptance criteria for the joint defect have been developed to ensure that the surface temperature of the monoblocks would not exceed the limit values [4] with discussion between IO and JADA. In the acceptance criteria of OVT, the specified size will be defined by performing NDE in CFC monoblocks of artificial defects [5][6][7][8].…”

Section: Nde By Infrared Thermographymentioning

confidence: 99%

Non-destructive examination with infrared thermography system for ITER divertor components

Seki

Ezato

Suzuki

et al. 2010

Fusion Engineering and Design

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Section: Nde By Infrared Thermographymentioning

confidence: 99%

Non-destructive examination with infrared thermography system for ITER divertor components

Seki

Ezato

Suzuki

et al. 2010

Fusion Engineering and Design

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“…During previous studies [6], it was calculated that the defects to be implemented into the CFC samples must respect the following rules of design:…”

Section: Artificial Defectsmentioning

confidence: 99%

Experimental activity on the definition of acceptance criteria for the ITER divertor plasma facing components

Escourbiac

Constans

Vignal

et al. 2009

Fusion Engineering and Design

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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%

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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Acceptance criteria for the ITER divertor vertical target

Cited by 16 publications

References 17 publications

Non-destructive examination with infrared thermography system for ITER divertor components

Non-destructive examination with infrared thermography system for ITER divertor components

Experimental activity on the definition of acceptance criteria for the ITER divertor plasma facing components

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

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