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Advanced gas-cooled nuclear reactor materials evaluation and development program: corrosion behavior of experimental alloys in controlled-purity helium at temperatures in the 750 to 1050/sup 0/C range. [Ni-20Cr + Al, Ti, Si, Nb and/or Y]
Author(s) -
D.W. McKee
Publication year - 1982
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/6774585
Subject(s) - yttrium , materials science , helium , metallurgy , corrosion , aluminium , chemistry , organic chemistry , oxide

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