LEADER 01821nam  2200409I  450 
001 9910705837103321
005 20170803132816.0
035   $a(CKB)5470000002454048
035   $a(OCoLC)999350634
035   $a(EXLCZ)995470000002454048
100   $a20170803j199809    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aAssessment of RELAP5/MOD3.1 using LSTF ten-percent main steam-line-break test run SB-SL-01 /$fprepared by J.G. Oh [and seven others]
210  1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dSeptember 1998.
215   $a1 online resource (viii, 111 pages) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0148
300   $a"Korea Power Engineering Company."
300   $a"Korea Institute of Nuclear Safety."
300   $a"Japan Atomic Energy Research Institute."
300   $a"September 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"G. Rhee, NRC project manager"--Bibliographic data sheet.
320   $aIncludes bibliographical references (page 29).
606   $aPressurized water reactors$xLoss of coolant$xComputer programs$xTesting
615  0$aPressurized water reactors$xLoss of coolant$xComputer programs$xTesting.
700   $aOh$b J. G.$01400314
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research.$bDivision of Systems Technology,
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910705837103321
996   $aAssessment of RELAP5$93466998
997   $aUNINA