Zirconium alloy heat treatment process and product

C - Chemistry – Metallurgy – 22 – C

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75/53, 148/55.8

C22C 16/00 (2006.01) C22F 1/18 (2006.01)

Patent

CA 1080513

ABSTRACT OF THE DISCLOSURE Zirconium-base alloy channels, fuel cladding tubes and other nuclear reactor structural components having unique resistance to accelerated pustular corrosion in the boiling water reactor environment are produced by a sequence of boat treatments causing segregation of intermetallic particulate precipitate phase in two dimensional arrays of particles of diameter from 100 to 400 Angstroms located d along grain boun- daries and sub-grain boundaries throughout the alloy

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