High heat flux behaviour of damaged plasma facing components

Fusion Engineering and Design

Volumn 56-57, Issue , 2001, Pages 285-290

  Escourbiac, F ^a   Chappuis, P ^a   Schlosser, J ^a   Merola, M ^b   Vastra, I ^c   Febvre, M ^c  

^a IRFM   (France)

^b EFDA CLOSE SUPPORT UNIT   (Germany)

^c AREVA NP   (France)

Author keywords

Fatigue testing; Infrared characterisation; Prototype; Vertical target

Indexed keywords

FATIGUE OF MATERIALS; FINITE ELEMENT METHOD; FUSION REACTOR DIVERTORS; HEAT FLUX; HEAT SINKS; INFRARED RADIATION; THERMAL EFFECTS;

BONDING DEFECTS; THERMAL FATIGUE TESTING;

EXPERIMENTAL REACTORS;

EID: 0035483788     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0920-3796(01)00301-5     Document Type: Article

References (5)

1. M. Merola et al., Manufacturing and testing of a prototypical divertor vertical target for ITER, Journal of Nuclear Materials 283-287 (2000).
2. G. Mayaux, M. Febvre et al, CEA report, DSM/DRFC/ STIF/Pco/91/04, September 1991.
3. A. Durocher et al., Interface quality control by infrared thermography measurement, Proc. on 15th World Conf. on NDT, Roma (Italy), 2000, to be published.
4. A. Durocher, Proc. of 20th SOFT, Marseille, pp. 121-124, 1998
5. J. Schlosser et al., Proc. of 15th UIT Nat. Heat Transfer Conf., pp. 45-59, 1997.