01763nam 2200421Ka 450 991069770460332120081209120324.0(CKB)5470000002391931(OCoLC)277230061(EXLCZ)99547000000239193120081209d2008 ua 0engtxtrdacontentcrdamediacrrdacarrierIrradiation-assisted stress corrosion cracking of austenitic stainless steels and alloy 690 from Halden phase-II irradiations[electronic resource] /prepared by Y. Chen ... [and others][Washington, D.C.] :U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,[2008]xviii, 48 pages, 14 unnumbered pages digital, PDF fileTitle from title screen (viewed on Dec. 8, 2008)."Argonne National Laboratory.""Date published: September 2008.""NUREG/CR-6965.""ANL-07/11."Boiling water reactorsNuclear reactorsMaterialsStress corrosionNuclear reactorsMaterialsEffect of radiation onBoiling water reactors.Nuclear reactorsMaterialsStress corrosion.Nuclear reactorsMaterialsEffect of radiation on.Chen Y1333782Argonne National Laboratory.U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research.GPOGPOBOOK9910697704603321Irradiation-assisted stress corrosion cracking of austenitic stainless steels and alloy 690 from Halden phase-II irradiations3504207UNINA