02219oam 2200529I 450 991070617630332120180717092100.0(CKB)5470000002454662(OCoLC)1029057502(EXLCZ)99547000000245466220180320d2017 ua 0engurmn|||||||||rdacontentrdamediardacarrierAssessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5 /prepared by Andrew Oussoren, J. Riznic, S.T. RevankarWashington, DC :Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,2017.1 online resource (xv, 29 pages) illustrations (some color)International agreement report ;NUREG/IA-0457"Manuscript completed: November 2015.""Date published: August 2017.""Prepared as part of the Agreement on Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."Includes bibliographical references (page 29).Pressurized water reactorsLoss of coolantNuclear power plantsPipingCrackingNuclear power plantsPipingCrackingfastPressurized water reactorsLoss of coolantfastOnline resources.Pressurized water reactorsLoss of coolant.Nuclear power plantsPipingCracking.Nuclear power plantsPipingCracking.Pressurized water reactorsLoss of coolant.Oussoren Andrew1416768Riznic Jovica R.Revankar ShripadU.S. Nuclear Regulatory Commission.Division of Systems Analysis,GPOGPOGPOMERUCOCLCAOCLCFBOOK9910706176303321Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP53526945UNINA