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100   $a20101201d2010      ua             0
101 0 $aeng
135   $aurbn|||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 00$aSCDAP/RELAP5 thermal-hydraulic evaluations of the potential for containment bypass during extended station blackout severe accident sequences in a Westinghouse four-loop PWR$b[electronic resource] /$fprepared by C.D. Fletcher ... [and others]
210  1$aWash9ngton, DC :$cU.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,$d[2010]
215   $a1 online resource (246 unnumbered pages) $cillustrations
300   $aTitle from PDF title screen (viewed on Dec. 1, 2010)..
300   $a"NUREG.CR-6995."
300   $a"C. Boyd, NRC point of contact."
300   $a"Manuscript completed: February 2010 ; date published: March 2010."
300   $a"NRC job code Y6198."
320   $aIncludes bibliographical references.
606   $aNuclear power plants
606   $aElectric power failures
606   $aPressurized water reactors$xAccidents
615  0$aNuclear power plants.
615  0$aElectric power failures.
615  0$aPressurized water reactors$xAccidents.
701   $aFletcher$b C. Don$01405089
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research.
801  0$bGPO
801  1$bGPO
801  2$bGPO
906   $aBOOK
912   $a9910699740903321
996   $aSCDAP$93480973
997   $aUNINA