01957nam 2200457I 450 991070574620332120170821093037.0(CKB)5470000002452946(OCoLC)1001433822(EXLCZ)99547000000245294620170821j201705 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierSteam line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment /prepared by Han-Sik Jung [and four others]Washington, DC :Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,May 2017.1 online resource (xi, 29 pages) illustrations (some color)International agreement report ;NUREG/IA-0474"Korea Institute of Nuclear Safety.""K. Tien, NRC project manager.""Manuscript completed: February 2016; date published: May 2017.""Prepared as part of the Agreement of Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."Includes bibliographical references (page 29).Nuclear power plantsPipingSafety measuresSteam-boilersNuclear reactorsCoolingSafety measuresNuclear power plantsUnited StatesNuclear power plantsPipingSafety measures.Steam-boilers.Nuclear reactorsCoolingSafety measures.Nuclear power plantsJung Han-Sik1392296U.S. Nuclear Regulatory Commission.Division of Systems Analysis,GPOGPOBOOK9910705746203321Steam line break analysis using RELAP53446792UNINA