Savannah River Site K-Reactor Probabilistic Safety Assessment [electronic resource]

This report gives the results of a Savannah River Site (SRS) K-Reactor Probabilistic Safety Assessment (PSA). Measures of adverse consequences to health and safety resulting from representations of severe accidents in SRS reactors are presented. In addition, the report gives a summary of the methods...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: Westinghouse Savannah River Company (Researcher), United States. Department of Energy. Savannah River Site (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, 1992.
Subjects:

MARC

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245 0 0 |a Savannah River Site K-Reactor Probabilistic Safety Assessment  |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 1992. 
300 |a 413 p. :  |b digital, PDF file. 
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500 |a Published through the Information Bridge: DOE Scientific and Technical Information. 
500 |a 12/01/1992. 
500 |a "wsrc-rp--91-041" 
500 |a "DE93040087" 
500 |a Bailey, R.T.; Baker, W.H.; Wittman, R.S.; Amos, C.N.; ÒKula, K.R.; Kearnaghan, D.P.; Brandyberry, M.D.; Woody, N.D.; Weingardt, J.J. 
513 |a Topical;  |b 12/01/1992. 
520 3 |a This report gives the results of a Savannah River Site (SRS) K-Reactor Probabilistic Safety Assessment (PSA). Measures of adverse consequences to health and safety resulting from representations of severe accidents in SRS reactors are presented. In addition, the report gives a summary of the methods employed to represent these accidents and to assess the resultant consequences. The report is issued to provide useful information to the U. S. Department of Energy (DOE) on the risk of operation of SRS reactors, for insights into severe accident phenomena that contribute to this risk, and in support of improved bases for other DOE programs in Heavy Water Reactor safety. 
536 |b AC09-89SR18035. 
650 7 |a K Reactor.  |2 local. 
650 7 |a Hydraulics.  |2 local. 
650 7 |a Criticality.  |2 local. 
650 7 |a Radiation Transport.  |2 local. 
650 7 |a Radiation Doses.  |2 local. 
650 7 |a Savannah River Plant.  |2 local. 
650 7 |a Explosions.  |2 local. 
650 7 |a Public Health.  |2 local. 
650 7 |a Reactor Safety.  |2 local. 
650 7 |a Meltdown.  |2 local. 
650 7 |a M Codes.  |2 local. 
650 7 |a Tritium.  |2 local. 
650 7 |a Containment Systems.  |2 local. 
650 7 |a Corium.  |2 local. 
650 7 |a Seismic Effects.  |2 local. 
650 7 |a Fuel Elements.  |2 local. 
650 7 |a Economics.  |2 local. 
650 7 |a Systems Analysis.  |2 local. 
650 7 |a Fuel-coolant Interactions.  |2 local. 
650 7 |a Safety Analysis.  |2 local. 
650 7 |a Data Covariances.  |2 local. 
650 7 |a Contamination.  |2 local. 
650 7 |a Risk Assessment.  |2 local. 
650 7 |a Heat Transfer.  |2 local. 
650 7 |a Fission Product Release.  |2 local. 
650 7 |a Loss Of Coolant.  |2 local. 
650 7 |a Source Terms.  |2 local. 
650 7 |a Reactor Components.  |2 local. 
650 7 |a Reactor Cooling Systems.  |2 local. 
650 7 |a Steam.  |2 local. 
650 7 |a General Studies Of Nuclear Reactors.  |2 edbsc. 
710 2 |a Westinghouse Savannah River Company.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |4 spn. 
710 1 |a United States.  |b Department of Energy.  |b Savannah River Site.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
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