LEADER 01870oam  2200421I  450 
001 9910711992803321
005 20191114101539.0
035   $a(CKB)5470000002488160
035   $a(OCoLC)1127579424
035   $a(EXLCZ)995470000002488160
100   $a20191114j201901    ua             0
101 0 $aeng
135   $aurmn|||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aSimulation of the LSTF-PKL Counterpart G7.1 Test at PKL facility using TRACE 5 /$fprepared by F. Sa?nchez [and three others]
210  1$aWashington, DC :$cDivision of System Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission,$dJanuary 2019.
215   $a1 online resource (xv, 27 pages) $cillustrations (chiefly color)
225 1 $aInternational agreement report ;$vNUREG/IA-0488
300   $a"January 2019."
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 27).
606   $aPressurized water reactors$xLoss of coolant$xComputer simulation
606   $aNuclear power plants$xAccidents$xComputer simulation
606   $aNuclear power plants$zGermany$zErlangen
615  0$aPressurized water reactors$xLoss of coolant$xComputer simulation.
615  0$aNuclear power plants$xAccidents$xComputer simulation.
615  0$aNuclear power plants
700   $aSa?nchez-Saez$b Francisco$01411570
712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Systems Analysis,
801  0$bGPO
801  1$bGPO
801  2$bGPO
906   $aBOOK
912   $a9910711992803321
996   $aSimulation of the LSTF-PKL Counterpart G7.1 Test at PKL facility using TRACE 5$93503157
997   $aUNINA