LEADER 02265oam 2200613 450 001 9910698568303321 005 20210309113739.0 035 $a(CKB)4330000001821133 035 $a(OCoLC)238650744 035 $a(OCoLC)1240732706 035 $a(EXLCZ)994330000001821133 100 $a20080805j199605 ua 0 101 0 $aeng 135 $aur||||||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aEffects of thermal aging on fracture toughness and charpy-impact strength of stainless steel pipe welds /$fprepared by D.J. Gavenda [and four others] 210 1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dMay 1996. 215 $a1 online resource (xiii, 72 pages) $cillustrations 300 $a"Argonne National Laboratory." 300 $a"Date published: May 1996." 300 $a"NUREG/CR-6428." 300 $a"ANL-95/47." 320 $aIncludes bibliographical references. 606 $aNuclear power plants$xPiping$xValves$xDeterioration 606 $aTemperature measuring instruments$zUnited States 606 $aNotched bar testing 606 $aNotched bar testing$2fast 606 $aNuclear power plants$xPiping$xValves$xDeterioration$2fast 606 $aTemperature measuring instruments$2fast 607 $aUnited States$2fast 608 $aTechnical reports.$2lcgft 615 0$aNuclear power plants$xPiping$xValves$xDeterioration. 615 0$aTemperature measuring instruments 615 0$aNotched bar testing. 615 7$aNotched bar testing. 615 7$aNuclear power plants$xPiping$xValves$xDeterioration. 615 7$aTemperature measuring instruments. 700 $aGavenda$b D. J.$01389462 712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Reactor Regulation, 712 02$aArgonne National Laboratory. 801 0$bGPO 801 1$bGPO 801 2$bOCLCQ 801 2$bOCLCF 801 2$bOCLCQ 801 2$bNJR 801 2$bOCLCQ 801 2$bGPO 906 $aBOOK 912 $a9910698568303321 996 $aEffects of thermal aging on fracture toughness and charpy-impact strength of stainless steel pipe welds$93441025 997 $aUNINA