LEADER 02223oam  2200517I  450 
001 9910704812803321
005 20131107131203.0
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100   $a20131025d2013      ua             0
101 0 $aeng
135   $aurcn|||||||||
181   $2rdacontent
182   $2rdamedia
183   $2rdacarrier
200 10$aAnalysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE /$fprepared by: S. Belai?d, J. Freixa, O. Zerkak
210  1$aWashington, DC :$cU.S. Nuclear Regulatory Commission,$d2013.
215   $a1 online resource (xiii, 29 pages) $ccolor illustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0432
300   $aTitle from title screen (viewed Oct. 25, 2013).
300   $a"September 2013."
320   $aIncludes bibliographical references (page 29).
517 3 $aAnalysis of the test Organisation for Economic Co-operation and Development-Primary Coolant Loop Test Facility G7.1 with the thermal-hydraulic system code TRACE
606   $aPressurized water reactors$xTesting
606   $aEmergency core cooling systems$xTesting
606   $aPressurized water reactors$xEquipment and supplies$xEffect of temperature on$xMeasurement
606   $aNuclear fuel claddings$xEffect of temperature on$xMeasurement
606   $aNuclear power plants$xSafety measures$xTesting
615  0$aPressurized water reactors$xTesting.
615  0$aEmergency core cooling systems$xTesting.
615  0$aPressurized water reactors$xEquipment and supplies$xEffect of temperature on$xMeasurement.
615  0$aNuclear fuel claddings$xEffect of temperature on$xMeasurement.
615  0$aNuclear power plants$xSafety measures$xTesting.
700   $aBelai?d$b S.$01417519
702   $aFreixa$b J.
702   $aZerkak$b O.
712 02$aU.S. Nuclear Regulatory Commission,
801  0$bGPO
801  1$bGPO
801  2$bGPO
906   $aBOOK
912   $a9910704812803321
996   $aAnalysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE$93526248
997   $aUNINA