02081oam 2200457I 450 991071151250332120191209110212.0(CKB)5470000002484930(OCoLC)1127640197(EXLCZ)99547000000248493020191114j201810 ua 0engurmn|||||||||txtrdacontentcrdamediacrrdacarrierUsing TRACE, MELCOR, CFD, and FRAPTRAN to establish the analysis methodology for Chinshan Nuclear Power Plant spent fuel pool /prepared by Jong-Rong Wang [and nine others]Washington, DC :Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,October 2018.1 online resource (xv, 33 pages) illustrations (some color)International agreement report ;NUREG/IA-0482"K. Tien, NRC project manager.""Manuscript completed: April 2017; Date published: October 2018.""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 (page 33).Boiling water reactorsTaiwanEvaluationNuclear power plantsTaiwanBoiling water reactorsTaiwanComputer simulationSpent reactor fuelsStorageTaiwanBoiling water reactorsEvaluation.Nuclear power plantsBoiling water reactorsComputer simulation.Spent reactor fuelsStorageWang Jong-Rong1397177U.S. Nuclear Regulatory Commission.Division of Systems Analysis,GPOGPOGPOBOOK9910711512503321Using TRACE, MELCOR, CFD, and FRAPTRAN to establish the analysis methodology for Chinshan Nuclear Power Plant spent fuel pool3462316UNINA