02221oam 2200481I 450 991070440470332120130830092638.0(CKB)5470000002441653(OCoLC)835137754(EXLCZ)99547000000244165320130403d2013 ua 0engurmn||||a||||txtrdacontentcrdamediacrrdacarrierCharacterization of thermal-hydraulic and ignition phenomena in prototypic, full-length boiling water reactor spent fuel pool assemblies after a postulated complete loss-of-coolant accident /prepared by E.R. Lindgren and S.G. Durbin ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory CommissionWashington, D.C. :United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,2013.1 online resource (247 unnumbered pages) color illustrationsTitle from title screen (viewed April 3, 2013)."NUREG/CR-7143.""SAND-2007-2270.""March 2013."Includes bibliographical references (page 197).Water cooled reactorsLoss of coolantComputer simulationSpent reactor fuelsAccidentsComputer simulationBoiling water reactorsAccidentsComputer simulationWater cooled reactorsLoss of coolantComputer simulation.Spent reactor fuelsAccidentsComputer simulation.Boiling water reactorsAccidentsComputer simulation.Lindgren Eric R.1393193Durbin S. G.U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research,Sandia Laboratories.GPOGPOGPOOCLCQGPOBOOK9910704404703321Characterization of thermal-hydraulic and ignition phenomena in prototypic, full-length boiling water reactor spent fuel pool assemblies after a postulated complete loss-of-coolant accident3449023UNINA