01633nam 2200397Ka 450 991069856710332120080811100530.0(CKB)4330000001896028(OCoLC)243464538(EXLCZ)99433000000189602820080811d2002 ua 0engtxtrdacontentcrdamediacrrdacarrierMechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments[electronic resource] /prepared by O.K. ChopraWashington, DC :Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,2002.xvi, 64 pages digital, PDF fileTitle from title screen (viewed on Aug. 11, 2008)."Argonne National Laboratory.""Date published: August 2002.""NUREG/CR-6787.""ANL-01/25."Austenitic stainless steelFatigueLight water reactorsMaterialsFatigueAustenitic stainless steelFatigue.Light water reactorsMaterialsFatigue.Chopra O. K1393760U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research.Division of Engineering Technology.Argonne National Laboratory.GPOGPOBOOK9910698567103321Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments3491684UNINA