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AbstractAbstract
[en] A tokamak experimental power reactor has been designed that is capable of producing net electric power over a wide range of possible operating conditions. A net production of 81MW of electricity is expected from the design reference conditions that assume a value of 0.07 for beta-toroidal, a maximum toroidal magnetic field of 9T and a thermal conversion efficiency of 30%. Impurity control is achieved through the use of a low-Z first wall coating. This approach allows a burn time of 60 seconds without the incorporation of a divertor. The system is cooled by a dual pressurized water/steam system that could potentially provide thermal efficiencies as high as 39%. The first surface facing the plasma is a low-Z coated water cooled panel that is attached to a 20cm thick blanket module. The vacuum boundary is removed 22cm from the plasma, thereby minimizing the amount of radiation damage in this vital component. It is estimated that the total system could be built for less than 550 million dollars. (author)
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); Panel proceedings series; p. 131-153; ISBN 92-0-131178-8;
; 1978; p. 131-153; IAEA; Vienna; Technical committee meeting and workshop on fusion reactor design; Madison, WI, USA; 10 - 21 Oct 1977; IAEA-TC--145/10

Record Type
Book
Literature Type
Conference
Country of publication
BETA RATIO, BIBLIOGRAPHIES, BREEDING BLANKETS, COST, ENERGY STORAGE, ENERGY TRANSFER, EXPERIMENTAL REACTORS, FIRST WALL, IMPURITIES, MAGNET COILS, MAGNETIC FIELDS, NEUTRAL ATOM BEAM INJECTION, PERFORMANCE, RELIABILITY, THERMONUCLEAR REACTOR MATERIAL, THERMONUCLEAR REACTORS, TOKAMAK DEVICES, TOROIDAL CONFIGURATION, TRITIUM RECOVERY
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