LEADER 01877oam 2200433I 450 001 9910705827603321 005 20170807120652.0 035 $a(CKB)5470000002454144 035 $a(OCoLC)999728892 035 $a(OCoLC)995470000002454144 035 $a(EXLCZ)995470000002454144 100 $a20170807j199808 ua 0 101 0 $aeng 135 $aur||||||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aAssessment of RELAP5/MOD3.2 with the LSTF experiment simulating a loss of residual heat removal event during mid-loop operation /$fprepared by K.W. Seul [and three others] 210 1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dAugust 1998. 215 $a1 online resource (various pagings) $cillustrations 225 1 $aInternational agreement report ;$vNUREG/IA-0143 300 $a"Korea Institute of Nuclear Safety, Advanced Reactor Dept." 300 $a"August 1998." 300 $a"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Maintenance Program (CAMP)." 300 $a"S. Smith, NRC project manager"--Bibliographic data sheet. 320 $aIncludes bibliographical references (page 65). 606 $aNuclear reactors$xCooling$xComputer simulation 606 $aNuclear reactor accidents$xComputer simulation 615 0$aNuclear reactors$xCooling$xComputer simulation. 615 0$aNuclear reactor accidents$xComputer simulation. 700 $aSeul$b K. W.$01395071 712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research, 801 0$bGPO 801 1$bGPO 801 2$bGPO 906 $aBOOK 912 $a9910705827603321 996 $aAssessment of RELAP5$93453065 997 $aUNINA