LEADER 01704nam  2200397I  450 
001 9910705829003321
005 20170807101057.0
035   $a(CKB)5470000002454129
035   $a(OCoLC)999728150
035   $a(EXLCZ)995470000002454129
100   $a20170807j199808    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aAssessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6 /$fprepared by T.S. Choi [and seven others]
210  1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dAugust 1998.
215   $a1 online resource (vi, 68, A38 pages) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0139
300   $a"Korea Nuclear Fuel Company."
300   $a"Korea Institute of Nuclear Safety, Advanced Reactor Dept."
300   $a"August 1998."
300   $a"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Maintenance Program (CAMP)."
300   $a"S. Smith, NRC project manager"--Bibliographic data sheet.
320   $aIncludes bibliographical references.
606   $aPressurized water reactors$xLoss of coolant$xComputer simulation
615  0$aPressurized water reactors$xLoss of coolant$xComputer simulation.
700   $aChoi$b T. S.$01416616
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research,
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910705829003321
996   $aAssessment of RELAP5$93522561
997   $aUNINA