Development of models for the evaluation of temperatures in a HTGR core following a loss of forced circulation and simultaneous reactor trip [electronic resource]

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Bibliographic Details
Online Access: Online Access (via OSTI)
Corporate Author: Oak Ridge National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Oak Ridge, Tenn. : Oak Ridge, Tenn. : Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1974.
Subjects:

MARC

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245 0 0 |a Development of models for the evaluation of temperatures in a HTGR core following a loss of forced circulation and simultaneous reactor trip  |h [electronic resource] 
260 |a Oak Ridge, Tenn. :  |b Oak Ridge National Laboratory. ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,  |c 1974. 
300 |a Pages: 69 :  |b digital, PDF file. 
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500 |a Published through SciTech Connect. 
500 |a 10/01/1974. 
500 |a "ornl-tm--4740" 
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500 |a Sanders, J.P.; Siman-Tov, I.I. 
536 |b W-7405-ENG-26. 
650 7 |a *Htgr Type Reactors-- Loss Of Flow.  |2 local. 
650 7 |a *Loss Of Flow-- Temperature Distribution.  |2 local. 
650 7 |a After-Heat.  |2 local. 
650 7 |a Comparative Evaluations.  |2 local. 
650 7 |a Configuration.  |2 local. 
650 7 |a Data.  |2 local. 
650 7 |a Mathematical Models.  |2 local. 
650 7 |a Scram.  |2 local. 
650 7 |a Temperature Gradients.  |2 local. 
650 7 |a Transients.  |2 local. 
650 7 |a Vrain Reactor.  |2 local. 
650 7 |a N77900* --Reactors--Reactor Safety & Environmental Aspects.  |2 edbsc. 
650 7 |a N77300 --Reactors--Power Reactors, Non-Breeding, Graphite Moderated.  |2 edbsc. 
710 2 |a Oak Ridge National Laboratory.  |4 res. 
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