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100   $a20130307j199306    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aAssessment of CCFL model of RELAP5/MOD3 against simple vertical tubes and rod bundle tests /$fprepared by S. Cho [and three others]
210  1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dJune 1993.
215   $a1 online resource (114 pages) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0100
300   $a"Korea Electric Power Corporation, Research Center."
300   $a"Korea Institute of Nuclear Safety."
300   $a"June 1993."
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"Type of report: technical"--Bibliographic data sheet.
320   $aIncludes bibliographical references.
606   $aPressurized water reactors$xAccidents$xComputer simulation
606   $aNuclear fuel rods$xTesting
615  0$aPressurized water reactors$xAccidents$xComputer simulation.
615  0$aNuclear fuel rods$xTesting.
700   $aCho$b S.$0532135
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research,
801  0$bLLB
801  1$bLLB
801  2$bOCLCO
801  2$bOCLCA
801  2$bOCLCQ
801  2$bGPO
906   $aBOOK
912   $a9910708490003321
996   $aAssessment of CCFL model of RELAP5$93498366
997   $aUNINA