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100   $a20170501j200405    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aCFD analysis of full-scale steam generator inlet plenum mixing during a PWR severe accident /$fC.F. Boyd, D.M. Helton, K. Hardesty
210  1$aWashington, DC :$cDivision of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dMay 2004.
215   $a1 online resource (xi, 72 pages) $cillustrations
300   $a"Publisher appears on title page as: Division of Systems Analysis and Regulatory Effevtiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission."
300   $a"NUREG-1788."
300   $a"Manuscript completed: May 2004; date published: May 2004."
320   $aIncludes bibliographical references.
517 3 $aCFD analysis of full scale steam generator inlet plenum mixing during a PWR severe accident
517 3 $aComputational fluid dynamics analysis of full-scale steam generator inlet plenum mixing during a pressurized-water reactor severe accident
606   $aPressurized water reactors$xAccidents
606   $aNuclear reactor accidents
606   $aNuclear power plants$xSafety measures
615  0$aPressurized water reactors$xAccidents.
615  0$aNuclear reactor accidents.
615  0$aNuclear power plants$xSafety measures.
700   $aBoyd$b Christopher Fred$01393894
702   $aHelton$b D. M.
702   $aHardesty$b K.
712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Systems Analysis and Regulatory Effectiveness,
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910705696803321
996   $aCFD analysis of full-scale steam generator inlet plenum mixing during a PWR severe accident$93453050
997   $aUNINA