Zirconium-base alloy nuclear fuel container and method

Metal treatment – Compositions – Heat treating

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148133, C22C 118

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active

041697430

ABSTRACT:
A fast neutron-irradiated zirconium-base alloy body having load-carrying capacity substantially greater than similar conventional zirconium-base alloy bodies likewise irradiated is produced by subjecting a body heat treated at 930.degree. C. and then water-quenched and containing 0.2 weight percent beryllium and at least 95 weight percent zirconium to integrated neutron flux approximating 1.2.times.10.sup.21 nvt while maintaining the body at about 330.degree. C.

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Welding Research Supplement, Jan. 1956, pp. 27s-31s.
WAPD-120, U.S. Atomic Energy Commission, Production Annealing of Zircaloy 2, 1968, pp. 6-17.
Ells et al., "The Irridation Response of a Group of Complex Zirconium Alloys", Irradiation Embrittlement and Creep in Fuel Cladding and Core Components, The British Nuclear Energy Society, London, 1972, pp. 43-46.

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