01689nam 2200385 450 991070583680332120170803134813.0(CKB)5470000002454051(OCoLC)999350910(EXLCZ)99547000000245405120170803j199907 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierRELAP5/MOD3.2 assessment using GERDA small break test, 1605AA /prepared by W. TeitschWashington, DC :Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,July 1999.1 online resource (31, A49, B62 pages) illustrationsInternational agreement report ;NUREG/IA-0166"ABB Reaktor GmbH.""July 1999.""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 Technology, Office of Nuclear Reactor Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet.Includes bibliographical references.Pressurized water reactorsLoss of coolantComputer simulationPressurized water reactorsLoss of coolantComputer simulation.Tietsch W.1393212U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research.Division of Systems Technology,GPOGPOBOOK9910705836803321RELAP53449073UNINA