Journal of Fusion Energy

, Volume 6, Issue 1, pp 65–88

Selection of a toroidal fusion reactor concept for a magnetic fusion production reactor

Authors

  • D. L. Jassby
    • Princeton Plasma Physics Laboratory
Contributed Papers

DOI: 10.1007/BF01053332

Cite this article as:
Jassby, D.L. J Fusion Energ (1987) 6: 65. doi:10.1007/BF01053332

Abstract

The basic fusion driver requirements of a toroidal materials production reactor are considered. The tokamak, stellarator, bumpy torus, and reversed-field pinch are compared with regard to their demonstrated performance, probable near-term development, and potential advantages and disadvantages if used as reactors for materials production. Of the candidate fusion drivers, the tokamak is determined to be the most viable for a near-term production reactor. Four tokamak reactor concepts (TORFA/FED-R, AFTR/ZEPHYR, Riggatron, and Superconducting Coil) of approximately 500-MW fusion power are compared with regard to their demands on plasma performance, required fusion technology development, and blanket configuration characteristics. Because of its relatively moderate requirements on fusion plasma physics and technology development, as well as its superior configuration of production blankets, the TORFA/FED-R type of reactor operating with a fusion power gain of about 3 is found to be the most suitable tokamak candidate for implementation as a near-term production reactor.

Key words

Magnetic fusion production reactortritium productionfusion breedertoroidal fusion reactor

Copyright information

© Plenum Publishing Corporation 1987