LEADER 02064oam 2200457I 450 001 9910707626103321 005 20161013130207.0 035 $a(CKB)5470000002466280 035 $a(OCoLC)960642349 035 $a(EXLCZ)995470000002466280 100 $a20161013j199007 ua 0 101 0 $aeng 135 $aur||||||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aAssessment study of RELAP5/MOD2 cycle 36.04 based on pressurizer safety and relief valve tests /$fprepared by E.J. Stubbe, L. Vanhoenacker 210 1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dJuly 1990. 215 $a1 online resource (37 pages) $cillustrations 225 1 $aInternational agreement report ;$vNUREG/IA-0034 300 $a"TRACTEBEL." 300 $a"July 1990." 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"Technical"--Bibliographic data sheet. 300 $a"Sponsoring organization: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet. 606 $aPressurized water reactors$xSafety measures$xSimulation methods 606 $aRelief valves$xTesting 606 $aPressurized water reactors$xLoss of coolant$xComputer programs 615 0$aPressurized water reactors$xSafety measures$xSimulation methods. 615 0$aRelief valves$xTesting. 615 0$aPressurized water reactors$xLoss of coolant$xComputer programs. 700 $aStubbe$b E. J$g(Elie J.),$01389174 702 $aVanhoenacker$b L. 712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research.$bDivision of Systems Research, 801 0$bGPO 801 1$bGPO 801 2$bGPO 906 $aBOOK 912 $a9910707626103321 996 $aAssessment study of RELAP5$93466876 997 $aUNINA