Open AccessTesting of Zircaloy-2-clad uranium seven-rod fuel elements. Final report
Author(s) -
G.T. Geering
Publication year - 1960
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - Uncategorized
Resource type - Reports
DOI - 10.2172/10151929
Subject(s) - rod , zirconium alloy , materials science , cladding (metalworking) , spent nuclear fuel , water cooled , uranium , corrosion , irradiation , metallurgy , aluminium , nuclear fuel , pressurized water reactor , burnup , nuclear engineering , zirconium , water cooling , engineering , mechanical engineering , nuclear physics , medicine , pathology , alternative medicine , physics
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