LEADER 01842nam 2200433Ka 450 001 9910699031103321 005 20091123102522.0 035 $a(CKB)5470000002399577 035 $a(OCoLC)468787386 035 $a(EXLCZ)995470000002399577 100 $a20091123d2009 ua 0 101 0 $aeng 135 $aurmn||||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aMethodology for estimating fabrication flaw density and distribution, reactor pressure vessel welds$b[electronic resource] /$fprepared by G.J. Schuster, M. Morra, S.R. Doctor 210 1$aWashington, DC :$cU.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,$d[2009] 215 $a1 online resource (95 unnumbered pages) $ccolor illustrations 300 $aTitle from title screen (viewed on Oct. 29, 2009). 300 $a"Pacific Northwest National Laboratory." 300 $a"Date published: May 2009." 300 $a"NUREG/CR-6989." 320 $aIncludes bibliographical references. 606 $aNuclear pressure vessels$xMaterials$xDeterioration$zUnited States 606 $aNuclear pressure vessels$xWelding$xDeterioration$zUnited States 615 0$aNuclear pressure vessels$xMaterials$xDeterioration 615 0$aNuclear pressure vessels$xWelding$xDeterioration 700 $aSchuster$b G. J$01409312 701 $aMorra$b M$g(Marino)$01409313 701 $aDoctor$b S. R$0316485 712 02$aPacific Northwest National Laboratory (U.S.) 712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research. 801 0$bGPO 801 1$bGPO 906 $aBOOK 912 $a9910699031103321 996 $aMethodology for estimating fabrication flaw density and distribution, reactor pressure vessel welds$93495371 997 $aUNINA