LEADER 01538nam 2200421I 450 001 9910702693403321 005 20140917144645.0 035 $a(CKB)5470000002429251 035 $a(OCoLC)890721783 035 $a(EXLCZ)995470000002429251 100 $a20140917d2014 ua 0 101 0 $aeng 135 $aurmn||||a|||| 181 $2rdacontent 182 $2rdamedia 183 $2rdacarrier 200 10$aAssessment of channel coolant voiding in RD-14M test facility using TRACE /$fprepared by Andrew Oussoren, Aleksandar Delja 210 1$aWashington, DC :$cU.S. Nuclear Regulatory Commission,$d2014. 215 $a1 online resource (65 unnumbered pages) $ccolor illustrations 225 1 $aNUREG/IA ;$v0446 300 $aTitle from title screen (viewed on Sept. 17, 2014). 300 $a"Manuscript completed: December 2013; date published: August 2014." 320 $aIncludes bibliographical references (page 41). 606 $aCANDU reactors$xAnalysis 606 $aNuclear reactors$xCooling 606 $aNuclear reactor accidents$xAnalysis 615 0$aCANDU reactors$xAnalysis. 615 0$aNuclear reactors$xCooling. 615 0$aNuclear reactor accidents$xAnalysis. 700 $aOussoren$b Andrew$01416768 702 $aDelja$b Aleksandar 712 02$aU.S. Nuclear Regulatory Commission, 801 0$bGPO 801 1$bGPO 906 $aBOOK 912 $a9910702693403321 996 $aAssessment of channel coolant voiding in RD-14M test facility using TRACE$93523193 997 $aUNINA