02223oam 2200517I 450 991070481280332120131107131203.0(CKB)5470000002445611(OCoLC)861495828(OCoLC)995470000002445611(EXLCZ)99547000000244561120131025d2013 ua 0engurcn|||||||||rdacontentrdamediardacarrierAnalysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE /prepared by: S. Belaïd, J. Freixa, O. ZerkakWashington, DC :U.S. Nuclear Regulatory Commission,2013.1 online resource (xiii, 29 pages) color illustrationsInternational agreement report ;NUREG/IA-0432Title from title screen (viewed Oct. 25, 2013)."September 2013."Includes bibliographical references (page 29).Analysis of the test Organisation for Economic Co-operation and Development-Primary Coolant Loop Test Facility G7.1 with the thermal-hydraulic system code TRACEPressurized water reactorsTestingEmergency core cooling systemsTestingPressurized water reactorsEquipment and suppliesEffect of temperature onMeasurementNuclear fuel claddingsEffect of temperature onMeasurementNuclear power plantsSafety measuresTestingPressurized water reactorsTesting.Emergency core cooling systemsTesting.Pressurized water reactorsEquipment and suppliesEffect of temperature onMeasurement.Nuclear fuel claddingsEffect of temperature onMeasurement.Nuclear power plantsSafety measuresTesting.Belaïd S.1417519Freixa J.Zerkak O.U.S. Nuclear Regulatory Commission,GPOGPOGPOBOOK9910704812803321Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE3526248UNINA