01772nam 2200421I 450 991070569650332120170501121859.0(CKB)5470000002451427(OCoLC)984994306(EXLCZ)99547000000245142720170501j200310 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierCFD analysis of 1/7th scale steam generator inlet plenum mixing during a PWR severe accident /prepared by C.F. Boyd, K. HardestyWashington, DC :Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,October 2003.1 online resource (various pagings) illustrations"NUREG-1781.""Manuscript completed: September 2003; date published: October 2003."Includes bibliographical references.Computational fluid dynamics analysis of one-seventh scale steam generator inlet plenum mixing during a pressurized-water reactor severe accidentPressurized water reactorsAccidentsNuclear reactor accidentsNuclear power plantsSafety measuresPressurized water reactorsAccidents.Nuclear reactor accidents.Nuclear power plantsSafety measures.Boyd Christopher Fred1393894Hardesty K.U.S. Nuclear Regulatory Commission.Division of Systems Analysis and Regulatory Effectiveness,GPOGPOBOOK9910705696503321CFD analysis of 13475322UNINA