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Title: Applications of the integrated-blanket-coil concept to the compact reversed-field pinch reactor

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5503687

Compact reactors, by their nature, are high-power-density devices. They place a premium on space usage within the system volume, and access to the fusion power core components is limited. The integrated-blanket-coil (IBC) concept relaxes some of these requirements by combining the functions of the breeding blanket with those of the magnet systems. In this paper, the IBC potential is analyzed for the compact reversed-field pinch reactor (CRFPR) coil sets: (a) the toroidal field (TF) system; (b) the polidal field (PF) system; (c) the ohmic heating (OH) subsystem of the PF system; and (d) the divertor coils in the impurity control system. Use is made of the Los Alamos National Laboratory (LANL) RFP systems code with suitable modifications, to estimate ohmic losses, coil masses, and economic (cost of electricity) impact of the different configurations. Preliminary evaluations indicate that a symmetric toroidal divertor would be suitable for the CRFPR. This presents a special attraction for use of IBC divertor coils. Since the minority field (TF) is < 1 T at the plasma edge, the required nulling current is modest. In addition, IBC coils can be placed closer to the plasma, allowing a trade-off between the higher resistive losses and reduced current requirements. Perhaps most importantly, use of IBC divertor coils would improve the tritium breeding ratio, which is somewhat marginal with copper divertor coils.

OSTI ID:
5503687
Report Number(s):
CONF-860610-; TRN: 88-008092
Journal Information:
Trans. Am. Nucl. Soc.; (United States), Vol. 52; Conference: American Nuclear Society annual meeting, Reno, NV, USA, 15 Jun 1986
Country of Publication:
United States
Language:
English