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100   $a20110426d2010      ua             0
101 0 $aeng
135   $aurmn|||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aSensitivity analyses of a hypothetical 6 inch break, LOCA in Asco? NPP using RELAP/MOD3.2$b[electronic resource] /$fprepared by R. Pericas, L. Batet, and F. Revento?s
210  1$aWashington, DC :$cU.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Systems Analysis,$d2010.
215   $a1 online resource (50 unnumbered pages) $ccolor illustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0240
300   $a"Date published: September 2010."
300   $aTitle from title screen (viewed on Apr. 22, 2011).
320   $aIncludes bibliographical references.
606   $aPressurized water reactors$xLoss of coolant
606   $aNuclear power plants$xAccidents
606   $aNuclear power plants$zSpain
615  0$aPressurized water reactors$xLoss of coolant.
615  0$aNuclear power plants$xAccidents.
615  0$aNuclear power plants
700   $aPericas$b R$01418031
701   $aBatet$b L$01393669
701   $aRevento?s$b F$01387562
712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Systems Analysis.
801  0$bGPO
801  1$bGPO
801  2$bGPO
906   $aBOOK
912   $a9910699966103321
996   $aSensitivity analyses of a hypothetical 6 inch break, LOCA in Asco? NPP using RELAP$93528250
997   $aUNINA