LEADER 02238oam 2200469I 450 001 9910707866403321 005 20161213112045.0 035 $a(CKB)5470000002467893 035 $a(OCoLC)925444398 035 $a(EXLCZ)995470000002467893 100 $a20151015j199306 ua 0 101 0 $aeng 135 $aur||||||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 00$a2D/3D Program work summary report /$fedited by P.S. Damerell, J. W. Simons 210 1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dJune 1993. 215 $a1 online resource (various pagings) $cillustrations 225 1 $aGRS ;$v100 225 1 $aInternational agreement report ;$v0126 300 $a"MPR-1345." 300 $a"Prepared jointly by Japan Atomic Energy Institute, Gesellschaft fuer Anlagen-und Reaktorsicherheit, Siemens AG, UB KWU, U.S. Nuclear Regulatory Commission, Los Alamos National Laboratory, MPR Associates, Inc." 300 $a"June 1993." 300 $a"Prepared as part of arrangement on Research Participation and Technical Exchange between the federal minister for research and technology of the Federal Republic of Germany (BMFT) and the Japan Atomic Energy Research Institute (JAERI) and the United States Nuclear Regulatory Commission (USNRC) in a coordinated analytical and experimental study of the thermo-hydraulic behavior of emergency core coolant during the refill and reflood phase of a loss-of-coolant accident in a pressurized water reactor (the 2D/3D Program)." 320 $aIncludes bibliographical references. 606 $aPressurized water reactors$xLoss of coolant 606 $aPressurized water reactors$xSafety measures 615 0$aPressurized water reactors$xLoss of coolant. 615 0$aPressurized water reactors$xSafety measures. 702 $aDamerell$b Paul S. 702 $aSimons$b J. W. 712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research, 801 0$bLLB 801 1$bLLB 801 2$bOCLCO 801 2$bOCLCQ 801 2$bGPO 906 $aBOOK 912 $a9910707866403321 996 $a2D$93265878 997 $aUNINA