LEADER 01905oam 2200433I 450 001 9910711905303321 005 20191120143749.0 035 $a(CKB)5470000002489044 035 $a(OCoLC)1128097666 035 $a(EXLCZ)995470000002489044 100 $a20191120j201902 ua 0 101 0 $aeng 135 $aurmn||||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aPost-test calculation of the PKL-2 test G7.1 using RELAP5/MOD3.3 /$fprepared by V. Martinez-Quiroga, F. Reventos, C. Pretel 210 1$aWashington, DC :$cDivision of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission,$dFebruary 2019. 215 $a1 online resource (xv, 17 pages) $cillustrations (chiefly color) 225 1 $aInternational agreement report ;$vNUREG/IA-0499 300 $a"Prepared as part of the Agreement on Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)." 300 $a"Kirk Tien, NRC project manager." 300 $a"Manuscript completed: November 2017; Date published: February 2019." 320 $aIncludes bibliographical references (page 17). 606 $aPressurized water reactors$xAccidents$xComputer simulation 606 $aNuclear power plants$xAccidents$xComputer programs 615 0$aPressurized water reactors$xAccidents$xComputer simulation. 615 0$aNuclear power plants$xAccidents$xComputer programs. 700 $aMarti?nez-Quiroga$b Victor$01408347 702 $aRevento?s$b F. 702 $aPretel$b C. 712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Systems Analysis, 801 0$bGPO 801 1$bGPO 801 2$bGPO 906 $aBOOK 912 $a9910711905303321 996 $aPost-test calculation of the PKL-2 test G7.1 using RELAP5$93491980 997 $aUNINA