02180oam 2200481I 450 991070512270332120140313140053.0(CKB)5470000002448132(OCoLC)872581811(OCoLC)995470000002448132(EXLCZ)99547000000244813220140313d2014 ua 0engurmn||||a||||txtrdacontentcrdamediacrrdacarrierAssessment of LONF ATWS for Maanshan PWR using TRACE code /prepared by: Jong-Rong Wang [and three others]Washington, DC :U.S. Nuclear Regulatory Commission,2014.1 online resource (53 unnumbered pages) color illustrationsInternational agreement report ;NUREG/IA-0436Title from title screen (viewed March 13, 2014)."February 2014.""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 (pages 6-1).Assessment of Loss Of Normal Feedwater Anticipated Transient Without Scram for Maanshan Pressurized Water Reactor using TRAC/RELAP Advanced Computational Engine codePressurized water reactorsChinaLoss of coolantComputer simulationPressurized water reactorsAccidentsChinaComputer simulationNuclear power plantsChinaComputer simulationNuclear power plantsChinaSafety measuresPressurized water reactorsLoss of coolantComputer simulation.Pressurized water reactorsAccidentsComputer simulation.Nuclear power plantsComputer simulation.Nuclear power plantsSafety measures.Wang Jong-Rong1397177U.S. Nuclear Regulatory Commission,GPOGPOGPOBOOK9910705122703321Assessment of LONF ATWS for Maanshan PWR using TRACE code3520110UNINA