Thermal-mechanical treatment of composite nuclear fuel element c

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

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376417, 29400N, G21C 320

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active

043904971

ABSTRACT:
Cladding for nuclear fuel elements which is formed with a zirconium metal barrier layer bonded to the inside surface of a zirconium alloy tube and which is sized by a cold working tube reduction process and is heat treated after final reduction at a temperature and for a time period which allows substantially complete recrystallization of the zirconium metal barrier layer and provides a fine-grained microstructure therein and which stress-relieves but does not fully recrystallize the zirconium alloy tube. The crystallographic structure of the zirconium metal barrier layer may be improved by compressive deformation such as shot-peening.

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Metallurgical Dictionary, (1/31/53) Reinhold Pub. Co. (N.Y.) Henderson et al., p. 206.

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