Open AccessEvaluation of ferritic alloy Fe-2-1/4Cr-1Mo after neutron irradiation - microstructure development
Author(s) -
D.S. Gelles
Publication year - 1984
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/7120109
Subject(s) - irradiation , materials science , void (composites) , fluence , microstructure , alloy , dislocation , ultimate tensile strength , atmospheric temperature range , analytical chemistry (journal) , number density , neutron , swelling , nuclear chemistry , metallurgy , radiochemistry , crystallography , composite material , chemistry , nuclear physics , thermodynamics , physics , chromatography
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