MARC

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035 |a (TOE)ost7116814 
035 |a (TOE)7116814 
040 |a TOE  |c TOE 
049 |a GDWR 
072 7 |a 21  |2 edbsc 
086 0 |a E 1.99:la-6666-ms 
086 0 |a E 1.99:la-6666-ms 
088 |a la-6666-ms 
245 0 0 |a Research on plasma core reactors  |h [electronic resource] 
260 |a Los Alamos, N.M. :  |b Los Alamos National Laboratory ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,  |c 1977. 
300 |a Pages: 10 :  |b digital, PDF file. 
336 |a text  |b txt  |2 rdacontent. 
337 |a computer  |b c  |2 rdamedia. 
338 |a online resource  |b cr  |2 rdacarrier. 
500 |a Published through the Information Bridge: DOE Scientific and Technical Information. 
500 |a 01/01/1977. 
500 |a "la-6666-ms" 
500 |a Helmick, H.H.; Bernard, W.; White, R.H.; Jarvis, G.A.; Barton, D.M. 
520 3 |a Experiments and theoretical studies are being conducted for NASA on critical assemblies with 1-m-diam by 1-m-long low-density cores surrounded by a thick beryllium reflector. These assemblies make extensive use of existing nuclear propulsion reactor components, facilities, and instrumentation. Due to excessive porosity in the reflector, the initial critical mass was 19 kg U(93.2). Addition of a 17-cm-thick by 89-cm-diam beryllium flux trap in the cavity reduced the critical mass to 7 kg when all the uranium was in the zone just outside the flux trap. A mockup aluminum UF₆ container was placed inside the flux trap and fueled with uranium-graphite elements. Fission distributions and reactivity worths of fuel and structural materials were measured. Finally, an 85,000-cm³ aluminum canister in the central region was fueled with UF₆ gas and fission density distributions determined. These results will be used to guide the design of a prototype plasma core reactor which will test energy removal by optical radiation. 
536 |b W-7405-ENG-36. 
650 7 |a Design.  |2 local. 
650 7 |a Uranium Hexafluoride.  |2 local. 
650 7 |a Gas Fueled Reactors.  |2 local. 
650 7 |a Zero Power Reactors.  |2 local. 
650 7 |a Experimental Reactors.  |2 local. 
650 7 |a Homogeneous Reactors.  |2 local. 
650 7 |a Reactors.  |2 local. 
650 7 |a Plasma Core Assembly.  |2 local. 
650 7 |a Uranium Compounds.  |2 local. 
650 7 |a Performance.  |2 local. 
650 7 |a Fluid Fueled Reactors.  |2 local. 
650 7 |a Fluorine Compounds.  |2 local. 
650 7 |a Research And Test Reactors.  |2 local. 
650 7 |a Actinide Compounds.  |2 local. 
650 7 |a Uranium Fluorides.  |2 local. 
650 7 |a Reactor Components.  |2 local. 
650 7 |a Halogen Compounds.  |2 local. 
650 7 |a Halides.  |2 local. 
650 7 |a Fluorides.  |2 local. 
650 7 |a Specific Nuclear Reactors And Associated Plants.  |2 edbsc. 
710 2 |a Los Alamos Scientific Laboratory.  |4 res. 
710 2 |a Los Alamos National Laboratory.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
856 4 0 |u http://www.osti.gov/servlets/purl/7116814-oJdHef/  |z Online Access 
907 |a .b72191211  |b 03-07-23  |c 11-08-12 
998 |a web  |b 11-08-12  |c f  |d m   |e p  |f eng  |g nmu  |h 0  |i 1 
956 |a Information bridge 
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952 f f |p Can circulate  |a University of Colorado Boulder  |b Online  |c Online  |d Online  |e E 1.99:la-6666-ms  |h Superintendent of Documents classification  |i web  |n 1