LEADER 01666nam 2200409Ka 450 001 9910698467103321 005 20080728163352.0 035 $a(CKB)4330000001837147 035 $a(OCoLC)236208922 035 $a(EXLCZ)994330000001837147 100 $a20080728d2008 ua 0 101 0 $aeng 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aFabrication flaw density and distribution in repairs to reactor pressure vessel and piping welds$b[electronic resource] /$fprepared by G.J. Schuster, F.A. Simonen, S.R. Doctor 210 1$aWashington, D.C. :$cU.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,$d[2008] 215 $a1 volume (various pagings) $cdigital, PDF file 300 $aTitle from title screen (viewed July 28, 2008). 300 $a"Pacific Northwest Laboratory." 300 $a"Date Published: April 2008." 300 $a"NUREG/CR-6945." 300 $a"PNNL-16726." 320 $aIncludes bibliographical references (page 8.1-8.3). 606 $aNuclear power plants$xPiping$xValves$xDeterioration 615 0$aNuclear power plants$xPiping$xValves$xDeterioration. 700 $aSchuster$b G. J$01409312 701 $aSimonen$b F. A$01387213 701 $aDoctor$b S. R$0316485 712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Risk Assessment and Special Projects. 712 02$aPacific Northwest Laboratory. 801 0$bGPO 801 1$bGPO 906 $aBOOK 912 $a9910698467103321 996 $aFabrication flaw density and distribution in repairs to reactor pressure vessel and piping welds$93509970 997 $aUNINA