COOLANT MIXING IN SODIUM COOLED FAST REACTOR FUEL BUNDLES. [electronic resource]

Reactors, Liquid Metal-cooled/coolant Mixing In Fuel Element Bundles Of Liquid Sodium-cooled Fast, Analytic Methods For Determining, (e/t); Reactor Fuel Elements/assemblies Of Liquid Sodium- Cooled Fast Reactor, Analysis Of Coolant Mixing In, (e/t); Reactors, Fast/coolant Mixing In Fuel Element Bund...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: U.S. Atomic Energy Commission. Division of Reactor Development and Technology (Researcher), United States. Department of Energy. Office of Scientific and Technical Information (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Oak Ridge, Tenn. : Oak Ridge, Tenn. : United States. Dept. of Energy. Office of Scientific and Technical Information ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1968.
Subjects:

MARC

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245 0 0 |a COOLANT MIXING IN SODIUM COOLED FAST REACTOR FUEL BUNDLES.  |h [electronic resource] 
260 |a Oak Ridge, Tenn. :  |b United States. Dept. of Energy. Office of Scientific and Technical Information ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,  |c 1968. 
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500 |a Published through the Information Bridge: DOE Scientific and Technical Information. 
500 |a 01/01/1968. 
500 |a "wash--1096" 
500 |a Wilson, L.W.; Todreas, N.E. 
520 0 |a Reactors, Liquid Metal-cooled/coolant Mixing In Fuel Element Bundles Of Liquid Sodium-cooled Fast, Analytic Methods For Determining, (e/t); Reactor Fuel Elements/assemblies Of Liquid Sodium- Cooled Fast Reactor, Analysis Of Coolant Mixing In, (e/t); Reactors, Fast/coolant Mixing In Fuel Element Bundles Of Liquid Sodium- Cooled, Analytic Methods For Determining, (e/t); Fluid Flow/ Mixing In Liquid Metal-cooled Fast Reactor Fuel Element Bundles Of Liquid Sodium Turbulent, Methods For, (e/t); Sodium/mixing In Fuel Element Bundles Of Liquid Metal-cooled Fast Reactors, Analysis Of, (e/t) 
650 7 |a Liquid Metal Coolant.  |2 local. 
650 7 |a Turbulence.  |2 local. 
650 7 |a Configuration.  |2 local. 
650 7 |a Fast Reactors.  |2 local. 
650 7 |a Analysis.  |2 local. 
650 7 |a Reactor Core.  |2 local. 
650 7 |a Reactors.  |2 local. 
650 7 |a Fast Neutrons.  |2 local. 
650 7 |a Fuel Elements.  |2 local. 
650 7 |a Fluid Flow.  |2 local. 
650 7 |a Sodium.  |2 local. 
710 2 |a U.S. Atomic Energy Commission.  |b Division of Reactor Development and Technology.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |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/4520997-dYD25L/  |z Online Access 
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