01769nam 2200421Ka 450 991069854500332120080814173059.0(CKB)4330000001819037(OCoLC)243787122(EXLCZ)99433000000181903720080814d2005 ua 0engtxtrdacontentcrdamediacrrdacarrierEffect of material heat treatment on fatigue crack initiation in austenitic stainless steels in LWR environments[electronic resource] /prepared by O.K. Chopra, B. Alexandreanu, and W.J. ShackWashington, DC :Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,[2005]xviii, 44 pages digital, PDF fileTitle from PDF title screen (viewed on Aug. 14, 2008)."Argonne National Laboratory.""Date published: July 2005.""NUREG/CR-6878.""ANL-03/35."Austenitic stainless steelFatigueLight water reactorsMaterialsFatigueAustenitic stainless steelFatigue.Light water reactorsMaterialsFatigue.Chopra O. K1393760Alexandreanu B1402236Shack W. J1393762U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research.Division of Engineering Technology.Argonne National Laboratory.GPOGPOBOOK9910698545003321Effect of material heat treatment on fatigue crack initiation in austenitic stainless steels in LWR environments3472351UNINA