LEADER 02204nam  2200505I  450 
001 9910707654803321
005 20160929095922.0
035   $a(CKB)5470000002465990
035   $a(OCoLC)959552387
035   $a(OCoLC)1050332808
035   $a(EXLCZ)995470000002465990
100   $a20160929j201605    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aConsequential SGTR analysis for Westinghouse and combustion engineering plants with thermally treated alloy 600 and 690 steam generator tubes $edraft report for comment /$fprepared by S. Sancaktar [and four others]
210  1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dMay 2016.
215   $a1 online resource (various pagings) $cillustrations
300   $a"NUREG-2195."
300   $a"Manuscript completed: February 2016; date published: May 2016."
300   $a"Innovative Engineering and Safety Solutions, LLC."
300   $a"Argonne National Laboratory."
300   $a"Performing organization: Division of Risk Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet.
320   $aIncludes bibliographic references.
517   $aConsequential SGTR analysis for Westinghouse and combustion engineering plants with thermally treated alloy 600 and 690 steam generator tubes 
606   $aSteam-boilers
606   $aTubes
606   $aCombustion engineering
606   $aNuclear power plants$xThermodynamics
606   $aSteel alloys
615  0$aSteam-boilers.
615  0$aTubes.
615  0$aCombustion engineering.
615  0$aNuclear power plants$xThermodynamics.
615  0$aSteel alloys.
700   $aSancaktar$b S.$01416175
712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Risk Analysis,
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910707654803321
996   $aConsequential SGTR analysis for Westinghouse and combustion engineering plants with thermally treated alloy 600 and 690 steam generator tubes$93520646
997   $aUNINA