LEADER 01904nam  2200409I  450 
001 9910706149303321
005 20170905105855.0
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035   $a(OCoLC)1002854085
035   $a(EXLCZ)995470000002454934
100   $a20170905j200007    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aAnalysis of the RELAP5/MOD3.2.2 beta critical flow models and assessment against critical flow data from the Marviken tests /$fprepared by C. Queral, J. Mulas, C.G. de la Rua
210  1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dJuly 2000.
215   $a1 online resource (xx, 74 pages) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0186
300   $a"Energy Systems Department, School of Mining Engineering, Polytechnic University of Madrid."
300   $a"July 2000."
300   $a"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP)."
300   $a"Sponsoring organization: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographical data sheet.
320   $aIncludes bibliographical references (pages 144-147).
606   $aNuclear reactors$xCooling$xComputer simulation
615  0$aNuclear reactors$xCooling$xComputer simulation.
700   $aQueral$b Ce?sar$01391246
702   $aMulas$b J.
702   $aDe la Rua$b C. G.
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research,
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910706149303321
996   $aAnalysis of the RELAP5$93515391
997   $aUNINA