The characterization of copper alloys for the application of fusion reactors
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)
- Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan)
Three kinds of candidate copper alloys for divertor structural materials of fusion experimental reactors, that is, Oxygen Free High thermal conductivity Copper (OFHC), alumina disperse reinforced copper (DSC) and the composite of W and Cu (W/Cu), were prepared for strength and fatigue tests at temperatures ranging from R.T. to 500 C in a vacuum. High temperature strength of DSC and W/Cu with rapid fracture after peak loading at the temperatures is higher than that of OFHC by factor of 2, but fracture strains of DFC and W/Cu are smaller than that of OFHC. Fatigue life of DSC, which shows the same fatigue behavior of OFHC at room temperature, is longer than other materials at 400 C. Remarkable fatigue life reduction of OFHC found in this experiment is to be due to recrystallization of OFHC yielded above 400 C.
- OSTI ID:
- 176130
- Report Number(s):
- CONF-950740-; ISBN 0-7918-1346-0; TRN: 96:003659
- Resource Relation:
- Conference: Joint American Society of Mechanical Engineers (ASME)/Japan Society of Mechanical Engineers (JSME) pressure vessels and piping conference, Honolulu, HI (United States), 23-27 Jul 1995; Other Information: PBD: 1995; Related Information: Is Part Of Fitness-for-service and decisions for petroleum and chemical equipment. PVP-Volume 315; Prager, M.; Becht, C. IV; Depadova, T.A.; Okazaki, M.; Onyewuenyi, O.A.; Smith, J.P.; Takezono, S.; Weingart, L.J.; Yagi, K. [eds.]; PB: 560 p.
- Country of Publication:
- United States
- Language:
- English
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