LEADER 02221oam 2200481I 450 001 9910704404703321 005 20130830092638.0 035 $a(CKB)5470000002441653 035 $a(OCoLC)835137754 035 $a(EXLCZ)995470000002441653 100 $a20130403d2013 ua 0 101 0 $aeng 135 $aurmn||||a|||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aCharacterization 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 /$fprepared by E.R. Lindgren and S.G. Durbin ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission 210 1$aWashington, D.C. :$cUnited States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,$d2013. 215 $a1 online resource (247 unnumbered pages) $ccolor illustrations 300 $aTitle from title screen (viewed April 3, 2013). 300 $a"NUREG/CR-7143." 300 $a"SAND-2007-2270." 300 $a"March 2013." 320 $aIncludes bibliographical references (page 197). 606 $aWater cooled reactors$xLoss of coolant$xComputer simulation 606 $aSpent reactor fuels$xAccidents$xComputer simulation 606 $aBoiling water reactors$xAccidents$xComputer simulation 615 0$aWater cooled reactors$xLoss of coolant$xComputer simulation. 615 0$aSpent reactor fuels$xAccidents$xComputer simulation. 615 0$aBoiling water reactors$xAccidents$xComputer simulation. 700 $aLindgren$b Eric R.$01393193 702 $aDurbin$b S. G. 712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research, 712 02$aSandia Laboratories. 801 0$bGPO 801 1$bGPO 801 2$bGPO 801 2$bOCLCQ 801 2$bGPO 906 $aBOOK 912 $a9910704404703321 996 $aCharacterization 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$93449023 997 $aUNINA