01772oam 2200445Ia 450 991069996610332120110913110844.0(CKB)5470000002406294(OCoLC)714831540(EXLCZ)99547000000240629420110426d2010 ua 0engurmn|||||||||txtrdacontentcrdamediacrrdacarrierSensitivity analyses of a hypothetical 6 inch break, LOCA in Ascó NPP using RELAP/MOD3.2[electronic resource] /prepared by R. Pericas, L. Batet, and F. ReventósWashington, DC :U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Systems Analysis,2010.1 online resource (50 unnumbered pages) color illustrationsInternational agreement report ;NUREG/IA-0240"Date published: September 2010."Title from title screen (viewed on Apr. 22, 2011).Includes bibliographical references.Pressurized water reactorsLoss of coolantNuclear power plantsAccidentsNuclear power plantsSpainPressurized water reactorsLoss of coolant.Nuclear power plantsAccidents.Nuclear power plantsPericas R1418031Batet L1393669Reventós F1387562U.S. Nuclear Regulatory Commission.Division of Systems Analysis.GPOGPOGPOBOOK9910699966103321Sensitivity analyses of a hypothetical 6 inch break, LOCA in Ascó NPP using RELAP3528250UNINA