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Reactor Materials Program: Mechanical properties of irradiated Types 304 and 304L stainless steel weldment components
Author(s) -
R.L. Sindelar,
G.R. Jr. Caskey
Publication year - 1991
Language(s) - English
Resource type - Reports
DOI - 10.2172/5084386
Subject(s) - materials science , irradiation , charpy impact test , welding , neutron flux , toughness , creep , piping , austenitic stainless steel , metallurgy , composite material , nuclear engineering , neutron , corrosion , environmental science , physics , quantum mechanics , environmental engineering , nuclear physics , engineering

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