LEADER 01769nam 2200433 450 001 9910706824003321 005 20180315093918.0 035 $a(CKB)5470000002459230 035 $a(OCoLC)1028732472 035 $a(EXLCZ)995470000002459230 100 $a20180315j199005 ua 0 101 0 $aeng 135 $aur||||||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aSteam Generator Tube Integrity Program/Steam Generator Group Project $efinal project summary report /$fprepared by R.J. Kurtz [and six others] 210 1$aWashington, DC :$cDivision of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dMay 1990. 215 $a1 online resource (various pagings) $cillustrations (some color) 300 $a"NUREG/CR-5117." 300 $a"PNL-6446; R5." 300 $a"Manuscript completed: April 1990; date published: May 1990." 300 $a"Pacific Northwest Laboratory." 320 $aIncludes bibliographical references. 517 $aSteam Generator Tube Integrity Program/Steam Generator Group Project 606 $aSteam-boilers$zUnited States$xTesting 606 $aSteam generating heavy water reactors$xTesting 606 $aPressurized water reactors$xTesting 615 0$aSteam-boilers$xTesting. 615 0$aSteam generating heavy water reactors$xTesting. 615 0$aPressurized water reactors$xTesting. 700 $aKurtz$b R. J.$01387164 712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research.$bDivision of Engineering, 801 0$bGPO 801 1$bGPO 906 $aBOOK 912 $a9910706824003321 996 $aSteam Generator Tube Integrity Program$93436700 997 $aUNINA