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001 9910705696503321
005 20170501121859.0
035   $a(CKB)5470000002451427
035   $a(OCoLC)984994306
035   $a(EXLCZ)995470000002451427
100   $a20170501j200310    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aCFD analysis of 1/7th scale steam generator inlet plenum mixing during a PWR severe accident /$fprepared by C.F. Boyd, K. Hardesty
210  1$aWashington, DC :$cDivision of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dOctober 2003.
215   $a1 online resource (various pagings) $cillustrations
300   $a"NUREG-1781."
300   $a"Manuscript completed: September 2003; date published: October 2003."
320   $aIncludes bibliographical references.
517 3 $aComputational fluid dynamics analysis of one-seventh 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   $aHardesty$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   $a9910705696503321
996   $aCFD analysis of 1$93475322
997   $aUNINA