LEADER 01925oam 2200445Ia 450 001 9910699380203321 005 20230902161550.0 035 $a(CKB)5470000002402111 035 $a(OCoLC)568687036 035 $a(EXLCZ)995470000002402111 100 $a20100324d2009 ua 0 101 0 $aeng 135 $aurcn||||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 00$aInvestigations of the VVER-1000 Coolant Transient Benchmark Phase 1 with the coupled code system RELAP5/PARCS$b[electronic resource] /$fprepared vy V. Sanchez-Espinoza 210 1$a[Washington, DC] :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$d[2009] 215 $a1 online resource (xiii, 39 pages) $ccolor illustrations 225 1 $aInternational agreement report 300 $aTitle from PDF title screen (viewed on Mar. 24, 2010). 300 $a"A Calvo, NRC project manager." 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"December 2009." 300 $a"NUREG/IA-0217." 320 $aIncludes bibliographical references (page 39). 410 0$aInternational agreement report. 606 $aNuclear reactors$xSafety measures 606 $aPressurized water reactors$xLoss of coolant 615 0$aNuclear reactors$xSafety measures. 615 0$aPressurized water reactors$xLoss of coolant. 701 $aSa?nchez-Espinoza$b Victor Hugo$01411577 712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research. 801 0$bGPO 801 1$bGPO 801 2$bGPO 906 $aBOOK 912 $a9910699380203321 996 $aInvestigations of the VVER-1000 Coolant Transient Benchmark Phase 1 with the coupled code system RELAP5$93509608 997 $aUNINA