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035   $a(EXLCZ)995470000002467149
100   $a20161110j199305    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aRELAP5 assessment using LSTF test data SB-CL-18 /$fprepared by S. Lee, B.D. Chung, H.J. Kim
210  1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dMay 1993.
215   $a1 online resource (xii, 206 pages) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0095
300   $a"Korea Institute of Nuclear Safety, Safety Analysis Department."
300   $a"May 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 report"--Bibliographic data sheet.
320   $aIncludes bibliographical references (page 27).
606   $aPressurized water reactors$xLoss of coolant$xComputer simulation
615  0$aPressurized water reactors$xLoss of coolant$xComputer simulation.
700   $aLee$b Sukho$01402929
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   $a9910707740103321
996   $aRELAP5 assessment using LSTF test data SB-CL-18$93474446
997   $aUNINA