01787nam 2200409I 450 991070774000332120161110133450.0(CKB)5470000002467150(OCoLC)962368578(EXLCZ)99547000000246715020161110j199306 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierRELAP5 assessment using semiscale SBLOCA test S-NH-1 /prepared by Euy-Joon Lee, Bub-Dong Chung, Hho-Jung KimWashington, DC :Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,June 1993.1 online resource (various pagings) illustrationsInternational agreement report ;NUREG/IA-0099"Safety Analysis Department, Korea Institute of Nuclear Safety.""June 1993.""Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP).""Type of report: technical"--Bibliographic data sheet.Includes bibliographical references (pages 22-23).Pressurized water reactorsLoss of coolantComputer simulationPressurized water reactorsLoss of coolantComputer simulation.Lee Euy-Joon1958-1417691Chung B. D(Bub Dong),Kim H. J(Hho Jung),U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research,GPOGPOBOOK9910707740003321RELAP5 assessment using semiscale SBLOCA test S-NH-13526967UNINA