LEADER 01725oam 2200433I 450 001 9910705176703321 005 20140224140240.0 035 $a(CKB)5470000002447587 035 $a(OCoLC)870971006 035 $a(OCoLC)995470000002447587 035 $a(EXLCZ)995470000002447587 100 $a20140224d2013 ua 0 101 0 $aeng 135 $aurmn||||a|||| 181 $2rdacontent 182 $2rdamedia 183 $2rdacarrier 200 10$aAssessment of RELAP5/MOD3.3 and TRACE V5.0 computer codes against LOCA test data from PSB-VVER test facility /$fprepared by M. Kync?l, R. Pernica 210 1$aWashington, DC :$cUnited States Nuclear Regulatory Commission,$d2013. 215 $a1 online resource (xvi, 183 pages) $ccolor illustrations 225 1 $aInternational agreement report ;$vNUREG/IA-0435 300 $a"December 2013." 300 $aTitle from title screen (viewed on Feb. 24, 2014). 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 (pages 83-84). 606 $aPressurized water reactors$xLoss of coolant$xComputer simulation 606 $aNuclear facilities$xComputer programs 615 0$aPressurized water reactors$xLoss of coolant$xComputer simulation. 615 0$aNuclear facilities$xComputer programs. 700 $aKync?l$b M.$01419117 702 $aPernica$b R. 712 02$aU.S. Nuclear Regulatory Commission, 801 0$bGPO 801 1$bGPO 801 2$bGPO 906 $aBOOK 912 $a9910705176703321 996 $aAssessment of RELAP5$93532648 997 $aUNINA