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U.S. Department of Energy
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High field compact tokamak reactor (HFCTR) conceptual design. Final report

Technical Report ·
OSTI ID:7129459

A conceptual design has been developed for a compact (R/sub 0/ = 6.0 m) high field (B/sub T/ = 7.4 T) tokamak demonstration power reactor which can produce fusion power densities as high as 10 MW/m/sup 3/ with a spatially averaged value of toroidal beta of less than 5%. The HFCTR design is based upon minimal extrapolation from experimentally established plasma confinement and MHD stability in tokamak devices. A unique design for the NB/sub 3/Sn toroidal-field magnet system reduces the stress in the high-field trunk region and allows the achievement of high fields with a small radial build. An integrated system of automated actuators, vacuum and current-carrying mechanical joints and flexible cryostats allow total modularization of the reactor, including the coil systems. A detailed estimate of maintenance operation time indicated the possibility of very high plant availability. The modest value of toroidal beta permits a simple plasma-shaping coil system, located inside the TF coil trunk. Heating of the central plasma is attained by the use of ripple-assisted injection of 120-keV D/sup 0/ beams, which is also used for dynamic control of the plasma temperature during the burn period. A FLIBE-lithium blanket is designed especially for high-power-density operation in a high-field environment, and gives an overall tritium breeding ratio of 1.05.

Research Organization:
Massachusetts Inst. of Tech., Cambridge (USA). Plasma Fusion Center
DOE Contract Number:
AC02-77ET52021
OSTI ID:
7129459
Report Number(s):
DOE/ET/52021-T1; ON: DE84008865
Country of Publication:
United States
Language:
English