Accession Number DE2013-1022667
Title Spherical Tokamak (ST) Transmutation of Nuclear Wastes.
Publication Date 2012
Media Count 7p
Personal Author E. T. Cheng J. Galambos J. Sheffield R. J. Cerbone Y. K. M. Peng
Abstract The concept for an ST fusion core that drives a He-cooled, actinide-bearing, molten-salt blanket of moderate power density to generate electricity is examined for the first time. The results show that the fusion core is suited for this purpose and require a level of plasma, power density, engineering, and material performances moderate in comparison with what has been considered desirable for fusion-only power plants. The low aspect ratio of ST introduces a relatively thick, diverted scrape-off layer which leads to reduced heat fluxes at the limiter and divertor tiles. The use of a demountable, water-cooled, single-turn copper center leg for the toroidal field coils enables simplifications of the fusion core configuration and improves overall practicality for future power applications. These result in much reduced size and cost of the fusion core for the transmutation power plant relative to an optimized fusion-only fusion core. Surrounded by a separate tritium-breeding zone, the molten-salt blanket concept is in principle less complex and costly than the thermal breeding blankets for fusion. These combine to effect major reductions in the cost and weight of the power core equipment for the transmutation power plant. The minimum cost of electricity for such a power plant is thus reduced from the best fusion-only counterpart by more than 30%, based on consistent but approximate modeling. The key issues, development steps, and the potential value inherent in the ST fusion core in addressing the world needs for nuclear waste reduction and energy production are discussed.
Keywords Aspect ratio
Breeding blankets
Configuration
Copper
Divertors
Electricity
Legs
Plasma confinement
Power density
Power plants
Production
Radioactive wastes
Simulation
Tokamak devices
Transmutation


 
Source Agency Technical Information Center Oak Ridge Tennessee
NTIS Subject Category 77A - Thermonuclear Fusion Devices
77G - Radioactive Wastes & Radioactivity
46G - Plasma Physics
Corporate Author Oak Ridge National Lab., TN.
Document Type Technical report
Title Note N/A
NTIS Issue Number 1323
Contract Number DE-AC05-00OR22725

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