DocumentCode
2555156
Title
Spherical tokamak (ST) transmutation of nuclear wastes
Author
Peng, Y.K.M. ; Cheng, E.T. ; Galambos, J.D. ; Cerbone, R.J.
Author_Institution
Oak Ridge Nat. Lab., TN, USA
Volume
2
fYear
1995
fDate
30 Sep-5 Oct 1995
Firstpage
1423
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
fusion reactor blankets; fusion reactor limiters; radioactive waste disposal; radioactive waste processing; Cu; He; He-cooled blanket; T; T-breeding zone; actinide-bearing blanket; diverted scrape-off layer; divertor tiles; fusion core; limiter; material performances; moderate power density; molten-salt blanket; nuclear wastes; reduced heat fluxes; spherical tokamak transmutation; toroidal field coils; water-cooled single-turn Cu center leg; Costs; Fusion power generation; Nuclear power generation; Plasma density; Plasma materials processing; Power engineering and energy; Power generation; Radioactive pollution; Tiles; Tokamaks;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location
Champaign, IL
Print_ISBN
0-7803-2969-4
Type
conf
DOI
10.1109/FUSION.1995.534492
Filename
534492
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