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Accession Number DE2013-1022675
Title System Studies of Copper-and Superconducting-Coil Pilot Plants.
Publication Date 2012
Media Count 6p
Personal Author C. Baker E. A. Chaniotakis J. Galambos L. Bromberg S. O. Dean Y. K. M. Peng
Abstract The TETRA systems code is used to examine devices with both normal copper and superconducting coils as vehicles for steady-state production of fusion power in a Pilot Plant. If the constraints of plasma ignition and net electrical power production are dropped, such devices are much smaller and less expensive than ITER-like devices. For wall loads near 0.5 MW/m2 with nominal ITER physics guidelines, devices with copper coils have major radii R near 2 m and direct costs near 1 x 10(9), while devices with superconducting coils have R = 4.1 m and costs of 2.4 x 10(9). However, the copper-coil devices have the burden of hundreds of megawatts of resistive power losses. All cases tend towards high aspect ratio (A > 4), high fields, and low current. The situation improves for the superconducting-coil cases if higher beta limits are permissible, whereas the copper-coil cases see less benefit from higher beta limits.
Keywords Copper
Pilot plants
Plasma confinement
Power generation
Power losses
Superconducting coils
Thermonuclear reactors

Source Agency Technical Information Center Oak Ridge Tennessee
NTIS Subject Category 77A - Thermonuclear Fusion Devices
46G - Plasma Physics
Corporate Author Oak Ridge National Lab., TN.
Document Type Technical report
Title Note N/A
NTIS Issue Number 1323
Contract Number DE-AC05-00OR22725

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