02336oam 2200505I 450 991071190710332120200122103623.0(CKB)5470000002489025(OCoLC)1128098618(OCoLC)995470000002489025(EXLCZ)99547000000248902520191120j201902 ua 0engurmn|||||||||txtrdacontentcrdamediacrrdacarrierIBLOCA analysis for Vandellós-NPP using RELAP5/MOD3.3 sensitivity calculations to EOP actions /prepared by M. Pérez-Ferrgut [and three others]Washington, DC :Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission,February 2019.1 online resource (xvii, 30 pages) illustrations (some color)International agreement report ;NUREG/IA-0497"Prepared as part of the Agreement on Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP).""K. Tien, NRC project manager.""Manuscript completed: January 2018; Date published: February 2019."Includes bibliographical references (pages 29-30).Intermediate Break Loss Of Coolant Accident analysis for Vandellós Nuclear Power Plant using RELAP5/MOD3.3 sensitivity calculations to Emergency Operaton Procedure actionsPressurized water reactorsAccidentsComputer simulationNuclear power plantsComputer programsNuclear power plantsAccidentsSpainNuclear power plantsComputer programsfastSpainfastPressurized water reactorsAccidentsComputer simulation.Nuclear power plantsComputer programs.Nuclear power plantsAccidentsNuclear power plantsComputer programs.Pérez-Ferrgut M.1406871U.S. Nuclear Regulatory Commission.Division of Systems Analysis,GPOGPOGPOOCLCFBOOK9910711907103321IBLOCA analysis for Vandellós-NPP using RELAP53486836UNINA