LEADER 01797nam 2200445I 450 001 9910707780003321 005 20161028153812.0 035 $a(CKB)5470000002466746 035 $a(OCoLC)961359366 035 $a(EXLCZ)995470000002466746 100 $a20161028d1992 ua 0 101 0 $aeng 135 $aur||||||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aAnalysis of semiscale test S-LH-1 using RELAP5/MOD2 /$fprepared by P.C. Hall, D.R. Bull 210 1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$d1992. 215 $a1 online resource (v, 32 pages) $cillustrations 225 1 $aInternational agreement report ;$vNUREG/IA-0064 300 $a"National Power Nuclear, Barnett Way." 300 $a"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP)." 300 $a"April 1992." 300 $a"GD/PE-N/725." 300 $a"PWR/HTWG/P(88)629(Rev)." 320 $aIncludes bibliographical references. 517 3 $aAnalysis of semiscale test S LH 1 using RELAP5/MOD2 606 $aPressurized water reactors$xTesting 606 $aEmergency core cooling systems$xTesting 615 0$aPressurized water reactors$xTesting. 615 0$aEmergency core cooling systems$xTesting. 700 $aHall$b P. C$g(Peter C.),$01404634 702 $aBull$b D. R$g(David R.), 712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research, 801 0$bGPO 801 1$bGPO 906 $aBOOK 912 $a9910707780003321 996 $aAnalysis of semiscale test S-LH-1 using RELAP5$93539476 997 $aUNINA