Review of direct energy conversion for fusion reactors [electronic resource]

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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, 1976.
Subjects:

MARC

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245 0 0 |a Review of direct energy conversion for fusion reactors  |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 1976. 
300 |a Pages: 21 :  |b digital, PDF file. 
336 |a text  |b txt  |2 rdacontent. 
337 |a computer  |b c  |2 rdamedia. 
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500 |a Published through the Information Bridge: DOE Scientific and Technical Information. 
500 |a 09/20/1976. 
500 |a "ucrl-78204" 
500 |a " conf-760935-5" 
500 |a 2. topical meeting on the technology of controlled nuclear fusion, Richland, WA, USA, 21 Sep 1976. 
500 |a Moir, R.W.; Barr, W.L. 
520 3 |a The direct conversion to electrical energy of the energy carried by the leakage plasma from a fusion reactor and by the ions that are not converted to neutrals in a neutral-beam injector is discussed. The conversion process is electrostatic deceleration and direct particle collection as distinct from plasma expansion against a time-varying magnetic field or conversion in an EXB duct (both MHD). Relatively simple 1-stage plasma direct converters are discussed which can have efficiencies of about 50 percent. More complex and costly (measured in $/kW) 2-, 3-, 4-, and 22-stage concepts have been tested at efficiencies approaching 90 percent. Beam direct converters have been tested at 15 keV and 2 kW of power at 70 +- 2 percent efficiency, and a test of a 120-keV, 1-MW version is being prepared. Designs for a 120-keV, 4-MW unit are presented. The beam direct converter, besides saving on power supplies and on beam dumps, should raise the efficiency of creating a neutral beam from 40 percent without direct conversion to 70 percent with direct conversion for a 120-keV deuterium beam. The technological limits determining power handling and lifetime such as space-charge effects, heat removal, electrode material, sputtering, blistering, voltage holding, and insulation design, are discussed. The application of plasma direct converters to toroidal plasma confinement concepts is also discussed. 
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650 7 |a Electric Potential.  |2 local. 
650 7 |a Electric Fields.  |2 local. 
650 7 |a Swelling.  |2 local. 
650 7 |a Electrodes.  |2 local. 
650 7 |a Efficiency.  |2 local. 
650 7 |a Direct Energy Converters.  |2 local. 
650 7 |a Sputtering.  |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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