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Title: Tokamak engineering test reactor

Technical Report ·
DOI:https://doi.org/10.2172/4175932· OSTI ID:4175932

The design criteria for a tokamak engineering test reactor can be met by operating in the two-component mode with reacting ion beams, together with a new blanket-shield design based on internal neutron spectrum shaping. A conceptual reactor design achieving a neutron wall loading of about 1 MW/m$sup 2$ is presented. The tokamak has a major radius of 3.05 m, the plasma cross-section is noncircular with a 2:1 elongation, and the plasma radius in the midplane is 55 cm. The total wall area is 149 m$sup 2$. The plasma conditions are T/sub e/ approximately T/sub i/ approximately 5 keV, and ntau approximately 8 x 10$sup 12$ cm$sup -3$s. The plasma temperature is maintained by injection of 177 MW of 200- keV neutral deuterium beams; the resulting deuterons undergo fusion reactions with the triton-target ions. The D-shaped toroidal field coils are extended out to large major radius (7.0 m), so that the blanket-shield test modules on the outer portion of the torus can be easily removed. The TF coils are superconducting, using a cryogenically stable TiNb design that permits a field at the coil of 80 kG and an axial field of 38 kG. The blanket-shield design for the inner portion of the torus nearest the machine center line utilizes a neutron spectral shifter so that the first structural wall behind the spectral shifter zone can withstand radiation damage for the reactor lifetime. The energy attenuation in this inner blanket is 8 x 10$sup -6$. If necessary, a tritium breeding ratio of 0.8 can be achieved using liquid lithium cooling in the outer blanket only. The overall power consumption of the reactor is about 340 MW(e). A neutron wall loading greater than 1 MW/m$sup 2$ can be achieved by increasing the maximum magnetic field or the plasma elongation. (auth)

Research Organization:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
DOE Contract Number:
E(11-1)-3073
NSA Number:
NSA-33-000332
OSTI ID:
4175932
Report Number(s):
MATT-1155
Resource Relation:
Other Information: Orig. Receipt Date: 30-JUN-76
Country of Publication:
United States
Language:
English