01797nam 2200445Ka 450 991069396870332120080812093933.0(CKB)4330000001845892(OCoLC)243603632(EXLCZ)99433000000184589220080812d2003 ua 0engtxtrdacontentcrdamediacrrdacarrierFracture toughness and crack growth rates of irradiated austenitic stainless steels[electronic resource] /prepared by O.K. Chopra, E.E. Gruber, W.J. ShackWashington, D.C. :Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,2003.xvi, 86 pages digital, PDF fileTitle from title screen (viewed on Aug. 12, 2008)."Argonne National Laboratory.""Date published: August 2003.""NUREG/CR-6826.""ANL-03/22."Nuclear power plantsPipingDeteriorationAustenitic stainless steelFractureFracture mechanicsNuclear power plantsPipingDeterioration.Austenitic stainless steelFracture.Fracture mechanics.Chopra O. K1393760Gruber E. E(Eugene E.),1933-1420541Shack W. J1393762U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research.Division of Engineering Technology.Argonne National Laboratory.GPOGPOBOOK9910693968703321Fracture toughness and crack growth rates of irradiated austenitic stainless steels3538833UNINA