System studies of copper- and superconducting-coil pilot plants

J. Galambos, C. Baker, Y. K.M. Peng, D. Cohn, M. Chaniotakis, L. Bromberg, S. O. Dean

Research output: Contribution to journalConference articlepeer-review

3 Scopus citations

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 1×109 $, while devices with superconducting coils have R = 4.1 m and costs of 2.4×109 $. 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.

Original languageEnglish
Pages (from-to)1759-1764
Number of pages6
JournalFusion Technology
Volume21
Issue number3 pt 2A
DOIs
StatePublished - 1992
EventProceedings of the 10th Topical Meeting on the Technology of Fusion Energy - Boston, MA, USA
Duration: Jun 7 1992Jun 12 1992

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