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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]
Mapping Intimacies
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10.2172/6774585
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1982
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Author(s):
D.W. McKee
Keyword(s):
Corrosion Behavior
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Nuclear Reactor
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Development Program
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Reactor Materials
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