Zirconium alloy fuel cladding resistant to PCI crack propagation

Details Zirconium alloy fuel cladding resistant to PCI crack propagation Zirconium alloy fuel cladding resistant to PCI crack propagation

1987-12-08

1988-10-04

Kyle, Deborah L.

Induced nuclear reactions: processes, systems, and elements

Fuel component structure

Encased with nonfuel component

420422, G21C 320

Patent

active

047755083

ABSTRACT:
This invention relates to a tubular water reactor fuel cladding having an outer cylindrical layer composed of a conventional zirconium base alloy. Bonded to the outer layer is a second, inner layer composed of an alloy consisting essentially of: about 0.1 to 0.3 wt. % tin; about 0.05 to 0.2 wt. % iron; about 0.05 to 0.4 wt. % niobium; about 0.03 to 0.1 wt. % of either chromium or nickel, alone or in combination with each other; while keeping the sum of the iron chromium and nickel contents below 0.25 wt. %; 300 to 1200 ppm oxygen; and the balance essentially zirconium. The inner layer is characterized by excellent resistance to PCI crack propagation, excellent aqueous corrosion resistance and a fully recrystallized microstructure.

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"The Development of the Zircaloys", Kass, ASTM-368, 1964, pp. 3-27.
"Zirconium and Zirconium Alloy Ingots for Nuclear Application", ASTM-B350-80, 1980.

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