CALCULATION OF DOPPLER COEFFICIENT AND OTHER SAFETY PARAMETERS FOR A LARGE FAST OXIDE REACTOR [electronic resource]

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Bibliographic Details
Online Access: Online Access
Corporate Author: General Electric Company (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Department of Energy. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1961.
Subjects:

MARC

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245 0 0 |a CALCULATION OF DOPPLER COEFFICIENT AND OTHER SAFETY PARAMETERS FOR A LARGE FAST OXIDE REACTOR  |h [electronic resource] 
260 |a Washington, D.C. :  |b United States. Department of Energy. ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,  |c 1961. 
300 |a Pages: 43 :  |b digital, PDF file. 
336 |a text  |b txt  |2 rdacontent. 
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338 |a online resource  |b cr  |2 rdacarrier. 
500 |a Published through SciTech Connect. 
500 |a 03/23/1961. 
500 |a "geap-3646" 
500 |a Greebler, P.; Hutchins, B.A.; Sueoka, J.R. 
520 3 |a Several safety parameters are calculated for a large, fast, Na-cooled, oxide-fueled reactor. The Doppler coefficient is studied as regards its effect on the reactivity during a power excursion, and its dependence on the neutron spectrum, on the concentrations of U/sup 238/, Pu /sup 239/ , a nd Pu/sup 240/, on spatial temperature and power distributions, and on temperature. Other parameters studied include the Na temperature coefficient of reactivity, and the reactivity insertion caused by total Na loss; reactivity coefficients caused by thermal expansion of fuel and steel cladding; the excess operating reactivity; and the reactivity caused by a fuel slump. The effects of a Be reflector on neutron lifetimes are determined. The safety aspects are balanced against economic considerations. (T.F.H.) 
536 |b AT(04-3)-189. 
650 7 |a Absorption.  |2 local. 
650 7 |a Beryllium.  |2 local. 
650 7 |a Canning.  |2 local. 
650 7 |a Distribution.  |2 local. 
650 7 |a Economics.  |2 local. 
650 7 |a Excursions.  |2 local. 
650 7 |a Expansion.  |2 local. 
650 7 |a Fast Neutrons.  |2 local. 
650 7 |a Fuel Cans.  |2 local. 
650 7 |a Fuel Elements.  |2 local. 
650 7 |a Fuels.  |2 local. 
650 7 |a Leaks.  |2 local. 
650 7 |a Lifetime.  |2 local. 
650 7 |a Liquid Metal Coolant.  |2 local. 
650 7 |a Neutrons.  |2 local. 
650 7 |a Operation.  |2 local. 
650 7 |a Oxides.  |2 local. 
650 7 |a Plutonium 239.  |2 local. 
650 7 |a Plutonium 240.  |2 local. 
650 7 |a Quantity Ratio.  |2 local. 
650 7 |a Reactivity.  |2 local. 
650 7 |a Reactor Safety.  |2 local. 
650 7 |a Reactors.  |2 local. 
650 7 |a Reflectors.  |2 local. 
650 7 |a Sodium.  |2 local. 
650 7 |a Spectra.  |2 local. 
650 7 |a Spectral Shift.  |2 local. 
650 7 |a Steels.  |2 local. 
650 7 |a Temperature.  |2 local. 
650 7 |a Uranium 238.  |2 local. 
650 7 |a Variations.  |2 local. 
650 7 |a Reactor Technology.  |2 edbsc. 
710 2 |a General Electric Company.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |4 spn. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
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