Production test IP-377-A, Irradiation of N-Reactor inner fuel tubes in the KER Loops
Author(s) -
W.K. Kratzer
Publication year - 1960
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/10175285
Subject(s) - brazing , irradiation , materials science , zirconium alloy , nuclear engineering , composite material , radiochemistry , nuclear chemistry , metallurgy , zirconium , chemistry , nuclear physics , physics , engineering , alloy
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