LEADER 01913nam 2200421I 450 001 9910705830503321 005 20170807084446.0 035 $a(CKB)5470000002454114 035 $a(OCoLC)999727152 035 $a(EXLCZ)995470000002454114 100 $a20170807j199809 ua 0 101 0 $aeng 135 $aur||||||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aAssessment of RELAP5/MOD3.2 for steam condensation experiments in the presence of noncondensibles in a vertical tube of PCCS /$fprepared by H. S. Park [and five others] 210 1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dSeptember 1998. 215 $a1 online resource (xvii, 91 pages) $cillustrations 225 1 $aInternational agreement report ;$vNUREG/IA-0147 300 $a"Korea Advanced Institute of Science & Technology." 300 $a"Korea Institute of Nuclear Safety." 300 $a"September 1998." 300 $a"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Maintenance Program (CAMP)." 300 $a"G. Rhee, NRC project manager"--Bibliographic data sheet. 320 $aIncludes bibliographical references (pages 63-65). 606 $aCondensation$xComputer simulation 606 $aPressurized water reactors$xLoss of coolant$xComputer simulation 615 0$aCondensation$xComputer simulation. 615 0$aPressurized water reactors$xLoss of coolant$xComputer simulation. 700 $aPark$b Hyeon-Sook$01393625 712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research.$bDivision of Systems Technology, 801 0$bGPO 801 1$bGPO 906 $aBOOK 912 $a9910705830503321 996 $aAssessment of RELAP5$93449909 997 $aUNINA