CFFTP FUSION PILOT-PLANT SCOPING STUDY

The CFFTP Pilot plant concept is a driven, steady-state I-I-mode tokam ak with ion cyclotron current drive. The fuel cycle uses low-tritium-i nventory technologies, including compact toroid fuelling. The mechanic al design is based on helium cooling, radial blanket maintenance, cera mic pebble breeder blanket, and demountable copper magnets. It is expe cted to operate for 1 full-power-year with 0.25 MW/m(2) average (0.4 M W/m(2) peak) neutron wall load. The machine would produce 20 MW of fus ion 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 diverters and an aspect ratio of 5. The total electric power consumption would be ar ound 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$Cdn, with a t otal project cost of 2.3 B$Cdn (1992). CFFTP Pilot would provide stead y-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 p ort area.