Corrosion resistant composite claddings for nuclear fuel rods

Details Corrosion resistant composite claddings for nuclear fuel rods Corrosion resistant composite claddings for nuclear fuel rods

1990-08-01

1991-06-18

Lechert, Jr., Stephen J.

Induced nuclear reactions: processes, systems, and elements

Fuel component structure

Encased with nonfuel component

376362, 376434, 376457, 420422, G21C 300

Patent

active

050248090

ABSTRACT:
A nuclear fuel element for use in the core of a nuclear reactor is disclosed having an improved corrosion resistant cladding. The cladding is comprised of zirconium alloys containing in weight percent 0.5 to 2.0 percent tin, or 0.5 to 2.5 percent bismuth, or 0.5 to 2.5 percent bismuth and tin, and about 0.5 to 1.0 percent of a solute composed of a member selected from the group consisting of molybdenum, niobium, tellurium and mixtures thereof, and the balance zirconium. Composite claddings are disclosed having a surface layer of one of the corrosion resistant zirconium alloys metallurgically bonded to a Zircaloy alloy tube. Claddings may contain an inner barrier layer of a moderate purity zirconium metallurgically bonded on the inside surface of the cladding to provide protection from fission products and gaseous impurities generated by the enclosed nuclear fuel.

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