01851oam 2200409I 450 991071178380332120191209104656.0(CKB)5470000002486230(OCoLC)1127639953(EXLCZ)99547000000248623020191114j201810 ua 0engurmn|||||||||txtrdacontentcrdamediacrrdacarrierLoss of flow analysis of Maanshan Nuclear Power Plant with RELAP5/SNAP /prepared by Chunkuan Shih [and six others]Washington, DC :Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,October 2018.1 online resource (xv, 59 pages) illustrations (some color)International agreement report ;NUREG/IA-0483"Prepared as part of the Agreement on Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP).""Manuscript completed: May 2017; date published: October 2018."Includes bibliographical references (page 59).Loss of flow analysis of Maanshan Nuclear Power Plant with RELAP5 Symbolic Nuclear Analysis ProgramNuclear power plantsTaiwanComputer programsPressurized water reactorsLoss of coolantNuclear power plantsComputer programs.Pressurized water reactorsLoss of coolant.Shih Chunkuan1389487U.S. Nuclear Regulatory Commission.Division of Systems Analysis,GPOGPOGPOBOOK9910711783803321Loss of flow analysis of Maanshan Nuclear Power Plant with RELAP53528147UNINA