Open AccessIRRADIATION OF A U-2% Zr FUEL TUBE IN THE VBWR
Author(s) -
H Quigley
Publication year - 1962
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4818425
Subject(s) - burnup , irradiation , zirconium alloy , materials science , cladding (metalworking) , alloy , boiling water reactor , swelling , zirconium , boiling , tube (container) , composite material , metallurgy , nuclear chemistry , nuclear engineering , chemistry , nuclear physics , physics , organic chemistry , engineering
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