LEADER 02219oam 2200529I 450 001 9910706176303321 005 20180717092100.0 035 $a(CKB)5470000002454662 035 $a(OCoLC)1029057502 035 $a(EXLCZ)995470000002454662 100 $a20180320d2017 ua 0 101 0 $aeng 135 $aurmn||||||||| 181 $2rdacontent 182 $2rdamedia 183 $2rdacarrier 200 10$aAssessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5 /$fprepared by Andrew Oussoren, J. Riznic, S.T. Revankar 210 1$aWashington, DC :$cDivision of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$d2017. 215 $a1 online resource (xv, 29 pages) $cillustrations (some color) 225 1 $aInternational agreement report ;$vNUREG/IA-0457 300 $a"Manuscript completed: November 2015." 300 $a"Date published: August 2017." 300 $a"Prepared as part of the Agreement on Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)." 320 $aIncludes bibliographical references (page 29). 606 $aPressurized water reactors$xLoss of coolant 606 $aNuclear power plants$xPiping$xCracking 606 $aNuclear power plants$xPiping$xCracking$2fast 606 $aPressurized water reactors$xLoss of coolant$2fast 608 $aOnline resources. 615 0$aPressurized water reactors$xLoss of coolant. 615 0$aNuclear power plants$xPiping$xCracking. 615 7$aNuclear power plants$xPiping$xCracking. 615 7$aPressurized water reactors$xLoss of coolant. 700 $aOussoren$b Andrew$01416768 702 $aRiznic$b Jovica R. 702 $aRevankar$b Shripad 712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Systems Analysis, 801 0$bGPO 801 1$bGPO 801 2$bGPO 801 2$bMERUC 801 2$bOCLCA 801 2$bOCLCF 906 $aBOOK 912 $a9910706176303321 996 $aAssessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5$93526945 997 $aUNINA