Engineering problems of the fusion breeder [electronic resource]

A study of fission suppressed blankets for the tandem mirror not only showed such blankets to be feasible but also to be safer than fissioning blankets. Such hybrids could produce enough fissile material to support up to 17 light water reactors of the same nuclear power rating. Beryllium was compare...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Lawrence Livermore National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Livermore, Calif : Oak Ridge, Tenn. : Lawrence Livermore National Laboratory ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1981.
Subjects:

MARC

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245 0 0 |a Engineering problems of the fusion breeder  |h [electronic resource] 
260 |a Livermore, Calif :  |b Lawrence Livermore National Laboratory ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,  |c 1981. 
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500 |a 9. symposium on engineering problems of fusion research, Chicago, IL, USA, 26 Oct 1981. 
500 |a Lee, J.D.; Barr, W.L.; Moir, R.W. 
520 3 |a A study of fission suppressed blankets for the tandem mirror not only showed such blankets to be feasible but also to be safer than fissioning blankets. Such hybrids could produce enough fissile material to support up to 17 light water reactors of the same nuclear power rating. Beryllium was compared to ⁷Li for neutron multiplication; both were considered feasible but the blanket with Li produced 20% less fissile fuel per unit of nuclear power in the reactor. The beryllium resource, while possibly being too small for extensive pure fusion application, would be adequate (with carefully planned industrial expansion) for the hybrid because of the large support ratio, and hence few hybrids required. Radiation damage and coatings for beryllium remain issues to be resolved by further study and experimentation. Molten salt reprocessing was compared to aqueous solution reprocessing (thorex). The molten salt reprocessing cost is $3.4/g fissile, whereas aqueous reprocessing cost $24 or $43/g for the thorium metal or oxide fuel form. 
536 |b W-7405-ENG-48. 
650 7 |a Hybrid Reactors.  |2 local. 
650 7 |a Lithium 7.  |2 local. 
650 7 |a Lithium Isotopes.  |2 local. 
650 7 |a Breeding Blankets.  |2 local. 
650 7 |a Odd-even Nuclei.  |2 local. 
650 7 |a Beryllium.  |2 local. 
650 7 |a Metals.  |2 local. 
650 7 |a Alkali Metal Isotopes.  |2 local. 
650 7 |a Separation Processes.  |2 local. 
650 7 |a Engineering.  |2 local. 
650 7 |a Alkaline Earth Metals.  |2 local. 
650 7 |a Tmr Reactors.  |2 local. 
650 7 |a Stable Isotopes.  |2 local. 
650 7 |a Isotopes.  |2 local. 
650 7 |a Magnetic Mirror Type Reactors.  |2 local. 
650 7 |a Reactor Components.  |2 local. 
650 7 |a Cost.  |2 local. 
650 7 |a Elements.  |2 local. 
650 7 |a Light Nuclei.  |2 local. 
650 7 |a Reprocessing.  |2 local. 
650 7 |a Nuclei.  |2 local. 
650 7 |a Thermonuclear Reactors.  |2 local. 
650 7 |a Plasma Physics And Fusion Technology.  |2 edbsc. 
710 2 |a Lawrence Livermore National Laboratory.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
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