01575nam 2200397I 450 991070785220332120161216122415.0(CKB)5470000002468036(OCoLC)966316949(EXLCZ)99547000000246803620161216j199306 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierRELAP5/MOD3 assessment using the semiscale 50% feed line break test S-FS-11 /prepared by E.J. Lee, B.D. Chung, H. J. KimWashington, DC :Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,June 1993.1 online resource (xv, 54, 102, 6 pages) illustrationsInternational agreement report ;NUREG/IA-0104"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)."Includes bibliographical references.Nuclear reactor accidentsComputer simulationNuclear reactor accidentsComputer simulation.Lee E. J.1392709Chung B. D.Kim H. J.U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research,GPOGPOBOOK9910707852203321RELAP53447865UNINA