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Title: Spherical tokamak (ST) transmutation of nuclear wastes

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 thusmore » 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.« less

Authors:
 [1];  [2];  [1];  [2]
  1. ORNL
  2. TSI Research Inc.
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
1022667
DOE Contract Number:  
DE-AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: 16th IEEE/NPSS Symposium on Fusion Engineering - Seeking a New Energy Era (SOFE 95), Champaign, IL, USA, 19951001, 19951001
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ASPECT RATIO; BREEDING BLANKETS; CONFIGURATION; COPPER; DIVERTORS; ELECTRICITY; LEGS; PLASMA; POWER DENSITY; POWER PLANTS; PRODUCTION; RADIOACTIVE WASTES; SIMULATION; TRANSMUTATION

Citation Formats

Peng, Yueng Kay Martin, Cheng, E. T., Galambos, John D, and Cerbone, R. J. Spherical tokamak (ST) transmutation of nuclear wastes. United States: N. p., 1995. Web.
Peng, Yueng Kay Martin, Cheng, E. T., Galambos, John D, & Cerbone, R. J. Spherical tokamak (ST) transmutation of nuclear wastes. United States.
Peng, Yueng Kay Martin, Cheng, E. T., Galambos, John D, and Cerbone, R. J. 1995. "Spherical tokamak (ST) transmutation of nuclear wastes". United States.
@article{osti_1022667,
title = {Spherical tokamak (ST) transmutation of nuclear wastes},
author = {Peng, Yueng Kay Martin and Cheng, E. T. and Galambos, John D and Cerbone, R. J.},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/1022667}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 1995},
month = {Sun Jan 01 00:00:00 EST 1995}
}

Conference:
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