01872nam 2200409I 450 991070614630332120170906095249.0(CKB)5470000002454965(OCoLC)1002926114(EXLCZ)99547000000245496520170906j200101 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierLBLOCA analysis in a Westinghouse PWR 3-loop design using RELAP5/MOD3 /prepared by J.I. Sánchez, C.A. Lage, T. NúñuzWashington, DC :Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,January 2001.1 online resource (ix, 61 pages) illustrationsInternational agreement report ;NUREG/IA-0195"Empresa Nacional del Uranio S.A.""January 2001.""Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP).""Sponsoring organization: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet.Includes bibliographical references (page 61).Pressurized water reactorsLoss of coolantComputer simulationPressurized water reactorsLoss of coolantComputer simulation.Sánchez J. I.1411146Lage C. A.Núñez T.U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research,GPOGPOBOOK9910706146303321LBLOCA analysis in a Westinghouse PWR 3-loop design using RELAP53501595UNINA