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|a (TOE)ost7341986
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|a (TOE)7341986
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|a TOE
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|a GDWR
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|a 70
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|a E 1.99: conf-760935-5
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|a E 1.99:ucrl-78204
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|a E 1.99: conf-760935-5
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|a ucrl-78204
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|a conf-760935-5
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|a Review of direct energy conversion for fusion reactors
|h [electronic resource]
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|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.
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|a Pages: 21 :
|b digital, PDF file.
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|a text
|b txt
|2 rdacontent.
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|a computer
|b c
|2 rdamedia.
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|a online resource
|b cr
|2 rdacarrier.
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|a Published through the Information Bridge: DOE Scientific and Technical Information.
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|a 09/20/1976.
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|a "ucrl-78204"
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|a " conf-760935-5"
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|a 2. topical meeting on the technology of controlled nuclear fusion, Richland, WA, USA, 21 Sep 1976.
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|a Moir, R.W.; Barr, W.L.
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|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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536 |
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|b W-7405-ENG-48.
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|a Electric Potential.
|2 local.
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|a Electric Fields.
|2 local.
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|a Swelling.
|2 local.
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|a Electrodes.
|2 local.
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|a Efficiency.
|2 local.
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|a Direct Energy Converters.
|2 local.
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|a Sputtering.
|2 local.
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|a Thermonuclear Reactors.
|2 local.
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|a Plasma Physics And Fusion Technology.
|2 edbsc.
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|a Lawrence Livermore National Laboratory.
|4 res.
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|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
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|u http://www.osti.gov/servlets/purl/7341986-vPtnDL/
|z Online Access
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|a .b72206755
|b 03-07-23
|c 11-08-12
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|a web
|b 11-08-12
|c f
|d m
|e p
|f eng
|g cau
|h 0
|i 1
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|a Information bridge
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|i 5a0c24b4-76b2-5ede-bc8c-073c74578f25
|s 55cc0fc5-663c-5dc0-9c8a-88bbba2456b8
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f |
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|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99: conf-760935-5
|h Superintendent of Documents classification
|i web
|n 1
|