Zirconium based alloy and component in a nuclear energy plant

Induced nuclear reactions: processes – systems – and elements – Fuel component structure – Encased with nonfuel component

Reexamination Certificate

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C376S416000, C148S421000, C420S422000

Reexamination Certificate

active

09857606

ABSTRACT:
A zirconium-based alloy, suitable for use in a corrosive environment, where it is subjected to increased radiation and comprises 0.5-1.6 percentage by weight Nb and 0.3-0.6 percentage by weight Fe. The alloy is characterised in that it comprises 0.5-0.85 percentage by weight Sn.

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