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UF6 breeder reactor power plants for electric power generationThe reactor concept analyzed is a U-233F6 core surrounded by a molten salt (Li(7)F, BeF2, ThF4) blanket. Nuclear survey calculations were carried out for both spherical and cylindrical geometries. Thermodynamic cycle calculations were performed for a variety of Rankine cycles. A conceptual design is presented along with a system layout for a 1000 MW stationary power plant. Advantages of the gas core breeder reactor (GCBR) are as follows: (1) high efficiency; (2) simplified on-line reprocessing; (3) inherent safety considerations; (4) high breeding ratio; (5) possibility of burning all or most of the long-lived nuclear waste actinides; and (6) possibility of extrapolating the technology to higher temperatures and MHD direct conversion.
Document ID
19780018923
Acquisition Source
Legacy CDMS
Document Type
Conference Paper
Authors
Rust, J. H.
(Ga. Inst. of Tech. Atlanta, United States)
Clement, J. D.
(Ga. Inst. of Tech. Atlanta, United States)
Hohl, F.
(NASA Langley Research Center Hampton, VA, United States)
Date Acquired
August 9, 2013
Publication Date
September 1, 1976
Publication Information
Publication: Princeton Univ. Partially Ionized Plasmas, Including the 3rd Symp. on Uranium Plasmas
Subject Category
Nuclear And High-Energy Physics
Accession Number
78N26866
Funding Number(s)
CONTRACT_GRANT: NSG-1168
CONTRACT_GRANT: NSG-7068
Distribution Limits
Public
Copyright
Work of the US Gov. Public Use Permitted.

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