PRELIMINARY ANALYSIS OF POSTULATED MAXIMUM ACCIDENTS FOR THE FFTF. [electronic resource]

Reactor Safety/accident Analysis For Fftf, Work Energy Release From Core Expansion In Maximum Hypothetical, (t); Fast Test Reactor/excursions In, Work Energy Release From Core Expansion In Maximum Hypothetical, (t)

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Bibliographic Details
Online Access: Online Access
Corporate Authors: Pacific Northwest Laboratory (Researcher), Pacific Northwest National Laboratory (U.S.) (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C : Oak Ridge, Tenn. : United States. Dept. of Energy ; 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 PRELIMINARY ANALYSIS OF POSTULATED MAXIMUM ACCIDENTS FOR THE FFTF.  |h [electronic resource] 
260 |a Washington, D.C :  |b United States. Dept. of Energy ;  |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 01/01/1968. 
500 |a "bnwl--760" 
500 |a Waltar, A.E.; Harris, R.A.; Simpson, D.E.; Fox, G.L. Jr.; Hagan, J.W.; Padilla, A. 
520 0 |a Reactor Safety/accident Analysis For Fftf, Work Energy Release From Core Expansion In Maximum Hypothetical, (t); Fast Test Reactor/excursions In, Work Energy Release From Core Expansion In Maximum Hypothetical, (t) 
536 |b AT(45-1)-1830. 
650 7 |a Evaporation.  |2 local. 
650 7 |a Ftr.  |2 local. 
650 7 |a Excursions.  |2 local. 
650 7 |a Analysis.  |2 local. 
650 7 |a Reactor Core.  |2 local. 
650 7 |a Energy.  |2 local. 
650 7 |a Reactor Safety.  |2 local. 
650 7 |a Mca.  |2 local. 
650 7 |a Accidents.  |2 local. 
650 7 |a Research Reactors.  |2 local. 
650 7 |a Expansion.  |2 local. 
650 7 |a Fftf.  |2 local. 
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710 1 |a United States.  |b Department of Energy.  |4 spn. 
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