CFFTP fusion pilot plant scoping study

Journal Article · Tue Nov 01 04:00:00 EST 1994 · Fusion Technology

OSTI ID:41545

Gierszewski, P; Blevins, J; Brunnader, H; Natalizio, A; Williams, G; Cumyn, P; Dean, B; Galambos, J; Holloway, C; Kelly, R ^[1]

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1. and others

The CFFTP Pilot plant concept is a driven, steady-state H-mode tokamak with ion cyclotron current drive. The fuel cycle uses low-tritium-inventory technologies, including compact toroid fuelling. The mechanical design is based on helium cooling, radial blanket maintenance, ceramic pebble breeder blanket, and demountable copper magnets. It is expected to operate for 1 full-power-year with 0.25 MW/m{sup 2} average (0.4 MW/m{sup 2} peak) neutron wall load. The machine would produce 20 MW of fusion power with 40 MW of auxiliary power. The 2.7 MA plasma current is ramped up inductively, and then sustained by the bootstrap current (32%) and fast wave current drive (68%). The plasma would be roughly the size of the TFTR plasma, but elongated with double-null divertors and an aspect ratio of 5. The total electric power consumption would be around 450 MWe. The tritium supply requirements, given partial breeding, would be only 0.8 kg. The on-site tritium inventory would be about 0.3 kg. The direct construction cost is estimated at 1.1 B$Cdn, with a total project cost of 2.3 B$Cdn (1992). CFFTP Pilot would provide steady-state integrated nuclear testing at a fluence and neutron wall load of about one-quarter ITER CDA, for a cost of about one-third ITER CDA. The blanket test area would be similar to the ITER CDA blanket test port area.

• OSTI ID: 41545
• Report Number(s): CONF-940630--
• Journal Information: Fusion Technology, Journal Name: Fusion Technology Journal Issue: 3 Vol. 26; ISSN 0748-1896; ISSN FUSTE8
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CANADA
DESIGN
H-MODE PLASMA CONFINEMENT
PILOT PLANTS
PROPOSALS
TOKAMAK DEVICES