01904nam 2200409I 450 991070614930332120170905105855.0(CKB)5470000002454934(OCoLC)1002854085(EXLCZ)99547000000245493420170905j200007 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierAnalysis of the RELAP5/MOD3.2.2 beta critical flow models and assessment against critical flow data from the Marviken tests /prepared by C. Queral, J. Mulas, C.G. de la RuaWashington, DC :Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,July 2000.1 online resource (xx, 74 pages) illustrationsInternational agreement report ;NUREG/IA-0186"Energy Systems Department, School of Mining Engineering, Polytechnic University of Madrid.""July 2000.""Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP).""Sponsoring organization: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographical data sheet.Includes bibliographical references (pages 144-147).Nuclear reactorsCoolingComputer simulationNuclear reactorsCoolingComputer simulation.Queral César1391246Mulas J.De la Rua C. G.U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research,GPOGPOBOOK9910706149303321Analysis of the RELAP53515391UNINA