Spherical tokamak (ST) transmutation of nuclear wastes

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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 ... continued below

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7 p.

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Peng, Y.-K.M.; Galambos, J.D.; Cheng, E.T. & Cerbone, R.J. December 31, 1995.

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Description

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 energy production are discussed.

Physical Description

7 p.

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INIS; OSTI as DE96005462

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  • 16. IEEE/NPSS symposium on fusion engineering, Champaign, IL (United States), 1-5 Oct 1995

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  • Other: DE96005462
  • Report No.: CONF-950905--25
  • Grant Number: AC05-84OR21400
  • Office of Scientific & Technical Information Report Number: 204697
  • Archival Resource Key: ark:/67531/metadc665512

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  • December 31, 1995

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  • June 29, 2015, 9:42 p.m.

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  • Jan. 21, 2016, 12:27 p.m.

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Peng, Y.-K.M.; Galambos, J.D.; Cheng, E.T. & Cerbone, R.J. Spherical tokamak (ST) transmutation of nuclear wastes, article, December 31, 1995; Tennessee. (digital.library.unt.edu/ark:/67531/metadc665512/: accessed August 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.