LEADER 01724oam 2200445Ia 450 001 9910701504803321 005 20120419102636.0 035 $a(CKB)5470000002420045 035 $a(OCoLC)786163587 035 $a(EXLCZ)995470000002420045 100 $a20120419d2012 ua 0 101 0 $aeng 135 $aurcn||||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aPost-test calculation of the ROSA/LSTF test 3-1 using RELAP5/Mod3.3$b[electronic resource] /$fprepared by V. Martinez, F. Revento?s, C. Pretel 210 1$aWashington, DC :$cU.S. Nuclear Regulatory Commission,$d[2012] 215 $a1 online resource (49 unnumbered pages) $ccolor illustrations 225 1 $aInternational agreement report ;$vNUREG/IA-0409 300 $a"Date published: March 2012." 300 $aTitle from title screen (viewed on Apr. 19, 2012). 320 $aIncludes bibliographical references (pages 7-1). 606 $aPressurized water reactors$xLoss of coolant$xComputer simulation 606 $aNuclear power plants$xAccidents$xComputer simulation 606 $aNuclear power plants$xComputer programs 615 0$aPressurized water reactors$xLoss of coolant$xComputer simulation. 615 0$aNuclear power plants$xAccidents$xComputer simulation. 615 0$aNuclear power plants$xComputer programs. 700 $aMartinez$b V$01405889 701 $aRevento?s$b F$01387562 701 $aPretel$b C$01405890 712 02$aU.S. Nuclear Regulatory Commission. 801 0$bGPO 801 1$bGPO 801 2$bGPO 906 $aBOOK 912 $a9910701504803321 996 $aPost-test calculation of the ROSA$93483278 997 $aUNINA