01666nam 2200409Ka 450 991069846710332120080728163352.0(CKB)4330000001837147(OCoLC)236208922(EXLCZ)99433000000183714720080728d2008 ua 0engtxtrdacontentcrdamediacrrdacarrierFabrication flaw density and distribution in repairs to reactor pressure vessel and piping welds[electronic resource] /prepared by G.J. Schuster, F.A. Simonen, S.R. DoctorWashington, D.C. :U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,[2008]1 volume (various pagings) digital, PDF fileTitle from title screen (viewed July 28, 2008)."Pacific Northwest Laboratory.""Date Published: April 2008.""NUREG/CR-6945.""PNNL-16726."Includes bibliographical references (page 8.1-8.3).Nuclear power plantsPipingValvesDeteriorationNuclear power plantsPipingValvesDeterioration.Schuster G. J1409312Simonen F. A1387213Doctor S. R316485U.S. Nuclear Regulatory Commission.Division of Risk Assessment and Special Projects.Pacific Northwest Laboratory.GPOGPOBOOK9910698467103321Fabrication flaw density and distribution in repairs to reactor pressure vessel and piping welds3509970UNINA