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100   $a20161110j199306    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aRELAP5 assessment using semiscale SBLOCA test S-NH-1 /$fprepared by Euy-Joon Lee, Bub-Dong Chung, Hho-Jung Kim
210  1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dJune 1993.
215   $a1 online resource (various pagings) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0099
300   $a"Safety Analysis Department, 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 (pages 22-23).
606   $aPressurized water reactors$xLoss of coolant$xComputer simulation
615  0$aPressurized water reactors$xLoss of coolant$xComputer simulation.
700   $aLee$b Euy-Joon$f1958-$01417691
702   $aChung$b B. D$g(Bub Dong),
702   $aKim$b H. J$g(Hho Jung),
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research,
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910707740003321
996   $aRELAP5 assessment using semiscale SBLOCA test S-NH-1$93526967
997   $aUNINA