01876oam 2200469I 450 991070849000332120161110140119.0(CKB)4330000001768912(OCoLC)873859677(EXLCZ)99433000000176891220130307j199306 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierAssessment of CCFL model of RELAP5/MOD3 against simple vertical tubes and rod bundle tests /prepared by S. Cho [and three others]Washington, DC :Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,June 1993.1 online resource (114 pages) illustrationsInternational agreement report ;NUREG/IA-0100"Korea Electric Power Corporation, Research Center.""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.Pressurized water reactorsAccidentsComputer simulationNuclear fuel rodsTestingPressurized water reactorsAccidentsComputer simulation.Nuclear fuel rodsTesting.Cho S.532135U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research,LLBLLBOCLCOOCLCAOCLCQGPOBOOK9910708490003321Assessment of CCFL model of RELAP53498366UNINA