LEADER 01959nam  2200445I  450 
001 9910707628003321
005 20161013104335.0
035   $a(CKB)5470000002466261
035   $a(OCoLC)960640659
035   $a(EXLCZ)995470000002466261
100   $a20161013j199004    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aAssessment of RELAP5/MOD2 code using loss of offsite power transient data of KNU #1 plant /$fprepared by Bud-Dong Chung, Hho-Jung Kim, Young-Jin Lee
210  1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dApril 1990.
215   $a1 online resource (v, 89 pages) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0030.
300   $a"Nuclear Safety Center, Korea Advanced Energy Research Institute."
300   $a"Department of Nuclear Engineering, Seoul National University."
300   $a"April 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.
320   $aIncludes bibliographical references (page 34).
606   $aPressurized water reactors$xSafety measures$xComputer programs
606   $aTransients (Dynamics)$xComputer programs
615  0$aPressurized water reactors$xSafety measures$xComputer programs.
615  0$aTransients (Dynamics)$xComputer programs.
700   $aChung$b B. D$g(Bub Dong),$01401000
702   $aKim$b H. J$g(Hho Jung),
702   $aLee$b Young Jin
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research,
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910707628003321
996   $aAssessment of RELAP5$93468987
997   $aUNINA