Open AccessTensile Testing on FFTF Irradiated Fast Reactor Cladding
Author(s) -
Tarik A. Saleh,
Tobias Romero,
Matthew Quintana
Publication year - 2018
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - Uncategorized
Resource type - Reports
DOI - 10.2172/1477593
Subject(s) - ultimate tensile strength , extrusion , materials science , cladding (metalworking) , perpendicular , tensile testing , irradiation , composite material , duct (anatomy) , structural engineering , engineering , mathematics , medicine , geometry , physics , pathology , nuclear physics
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