01842nam 2200433Ka 450 991069903110332120091123102522.0(CKB)5470000002399577(OCoLC)468787386(EXLCZ)99547000000239957720091123d2009 ua 0engurmn|||||||||txtrdacontentcrdamediacrrdacarrierMethodology for estimating fabrication flaw density and distribution, reactor pressure vessel welds[electronic resource] /prepared by G.J. Schuster, M. Morra, S.R. DoctorWashington, DC :U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,[2009]1 online resource (95 unnumbered pages) color illustrationsTitle from title screen (viewed on Oct. 29, 2009)."Pacific Northwest National Laboratory.""Date published: May 2009.""NUREG/CR-6989."Includes bibliographical references.Nuclear pressure vesselsMaterialsDeteriorationUnited StatesNuclear pressure vesselsWeldingDeteriorationUnited StatesNuclear pressure vesselsMaterialsDeteriorationNuclear pressure vesselsWeldingDeteriorationSchuster G. J1409312Morra M(Marino)1409313Doctor S. R316485Pacific Northwest National Laboratory (U.S.)U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research.GPOGPOBOOK9910699031103321Methodology for estimating fabrication flaw density and distribution, reactor pressure vessel welds3495371UNINA