LOFT advanced densitometer for nuclear loss-of-coolant experiments [electronic resource]

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Bibliographic Details
Online Access: Online Access
Main Authors: Lassahn, G.D (Author), Wood, D.B (Author), Johnson, L.O (Author)
Corporate Author: Idaho National Engineering Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Oak Ridge, Tenn. : distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1979.
Subjects:

MARC

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245 0 0 |a LOFT advanced densitometer for nuclear loss-of-coolant experiments  |h [electronic resource] 
260 |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,  |c 1979. 
300 |a Pages: 7 :  |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 SciTech Connect. 
500 |a 01/01/1979. 
500 |a "conf-790505-6" 
500 |a 25. ISA international instrumentation symposium, Anaheim, CA, USA, 7 May 1979. 
500 |a Lassahn, G.D.; Wood, D.B.; Johnson, L.O. 
500 |a Idaho National Engineering Lab., Idaho Falls (USA) 
520 3 |a A ''nuclear hardened'' gamma densitometer, a device which uses radiation attenuation to measure fluid density in the presence of a background radiation field, is described. Data from the nuclear hardened gamma densitometer are acquired by time sampling the coolant fluid piping and fluid attenuated source energy spectrum. The data are used to calculate transient coolant fluid cross sectional average density to analyze transient mass flow and other thermal-hydraulic characteristics during the Loss-of-Fluid Test (LOFT) loss-of-coolant experiments. The nuclear hardened gamma densitometer uses a pulse height analysis or energy discrimination, pulse counting technique which makes separation of the gamma radiation source signal from the reactor generated gamma radiation background noise signal possible by processing discrete pulses which retain their pulse amplitude information. 
536 |b EY-76-C-07-1570. 
650 7 |a Loft Reactor.  |2 local. 
650 7 |a Densitometers.  |2 local. 
650 7 |a Data Processing.  |2 local. 
650 7 |a Reactor Instrumentation.  |2 local. 
650 7 |a Specifications.  |2 local. 
650 7 |a Measuring Instruments.  |2 local. 
650 7 |a Photometers.  |2 local. 
650 7 |a Processing.  |2 local. 
650 7 |a Pwr Type Reactors.  |2 local. 
650 7 |a Reactors.  |2 local. 
650 7 |a Research And Test Reactors.  |2 local. 
650 7 |a Tank Type Reactors.  |2 local. 
650 7 |a Test Reactors.  |2 local. 
650 7 |a Water Cooled Reactors.  |2 local. 
650 7 |a Water Moderated Reactors.  |2 local. 
650 7 |a Specific Nuclear Reactors And Associated Plants.  |2 edbsc. 
700 1 |a Lassahn, G.D.  |4 aut. 
700 1 |a Wood, D.B.  |4 aut. 
700 1 |a Johnson, L.O.  |4 aut. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
710 2 |a Idaho National Engineering Laboratory  |4 res. 
856 4 0 |u http://www.osti.gov/servlets/purl/6309135/  |z Online Access 
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