01707nam 2200397 a 450 991069784700332120081210162826.0(CKB)5470000002392513(OCoLC)277768868(EXLCZ)99547000000239251320081210d2007 ua 0engurcn||||a||||txtrdacontentcrdamediacrrdacarrierAssessment of eddy current testing for the detection of cracks in cast stainless steel reactor piping components[electronic resource] /prepared by A.A. Diaz ... [and others]Washington, DC :Division of Fuel, Engineering, and Radiological Research, Division of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,2007.1 volume (various pagings) digital, PDF fileTitle from title screen (viewed on Dec. 10, 2008)."Pacific Northwest National Laboratory.""Date published: February 2007.""NUREG/CR-6929.""PNNL-16253."Includes bibliographical references (pages 8-1 - 8-2).Nuclear power plantsPipingCrackingNuclear power plantsPipingCracking.Diaz Aaron A1408182U.S. Nuclear Regulatory Commission.Division of Fuel, Engineering, and Radiological Research.Pacific Northwest National Laboratory (U.S.)GPOGPOBOOK9910697847003321Assessment of eddy current testing for the detection of cracks in cast stainless steel reactor piping components3504931UNINA