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100   $a20191120j201902    ua             0
101 0 $aeng
135   $aurmn|||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aIBLOCA analysis for Vandello?s-NPP using RELAP5/MOD3.3 sensitivity calculations to EOP actions /$fprepared by M. Pe?rez-Ferrgut [and three others]
210  1$aWashington, DC :$cDivision of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission,$dFebruary 2019.
215   $a1 online resource (xvii, 30 pages) $cillustrations (some color)
225 1 $aInternational agreement report ;$vNUREG/IA-0497
300   $a"Prepared as part of the Agreement on Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."
300   $a"K. Tien, NRC project manager."
300   $a"Manuscript completed: January 2018; Date published: February 2019."
320   $aIncludes bibliographical references (pages 29-30).
517 3 $aIntermediate Break Loss Of Coolant Accident analysis for Vandello?s Nuclear Power Plant using RELAP5/MOD3.3 sensitivity calculations to Emergency Operaton Procedure actions
606   $aPressurized water reactors$xAccidents$xComputer simulation
606   $aNuclear power plants$xComputer programs
606   $aNuclear power plants$xAccidents$zSpain
606   $aNuclear power plants$xComputer programs$2fast
607   $aSpain$2fast
615  0$aPressurized water reactors$xAccidents$xComputer simulation.
615  0$aNuclear power plants$xComputer programs.
615  0$aNuclear power plants$xAccidents
615  7$aNuclear power plants$xComputer programs.
700   $aPe?rez-Ferrgut$b M.$01406871
712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Systems Analysis,
801  0$bGPO
801  1$bGPO
801  2$bGPO
801  2$bOCLCF
906   $aBOOK
912   $a9910711907103321
996   $aIBLOCA analysis for Vandello?s-NPP using RELAP5$93486836
997   $aUNINA