01821nam 2200433Ka 450 991069721210332120080804120223.0(CKB)5470000002386805(OCoLC)237787622(EXLCZ)99547000000238680520080804d1990 ua 0engtxtrdacontentcrdamediacrrdacarrierInitial assessment of the mechanisms and significance of low-temperature embrittlement of cast stainless steels in LWR systems[electronic resource] /prepared by O.K. Chopra, A. SatherWashington, DC :Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,1990.1 volume (various pagings) digital, PDF fileTitle from title screen (viewed on Aug. 4, 2008)."Argonne National Laboratory.""Date published: August 1990.""NUREG/CR-5385.""ANL-89/17."Steel, CastEffect of temperature onTestingLight water reactorsMaterialsFatigueStainless steelFatigueSteel, CastEffect of temperature onTesting.Light water reactorsMaterialsFatigue.Stainless steelFatigue.Chopra O. K1393760Sather A1396777U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research.Division of Engineering.Argonne National Laboratory.GPOGPOBOOK9910697212103321Initial assessment of the mechanisms and significance of low-temperature embrittlement of cast stainless steels in LWR systems3457431UNINA