Zirconium alloy absorber layer

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

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376339, 376416, G21C 300

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active

052672905

ABSTRACT:
A burnable-absorber-containing zirconium alloy is described for application to the inside surface of cladding tubes for light water nuclear reactors. The alloy comprises naturally occurring erbium in a range from a measurable amount up to about 20 wt. % or isotopically purified erbium-167 in a range from a measurable amount up to about 5 wt. %; tin in a range from a measurable amount up to about 0.5 wt. %; iron in a range from a measurable amount up to about 0.2 wt. %; chromium in a range from a measurable amount up to about 0.1 wt. %; niobium in a range from a measurable amount up to about 0.1 wt. %; silicon in a range from about 50 to about 120 parts per million ("ppm"); oxygen in a range from a measurable amount up to about 800 ppm; and the balance zirconium. Such an alloy provides an effective absorber material for reactor control, while providing adequate mechanical properties and corrosion resistance for the intended application.

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Metallurgical Progress Report, No. 3, pp. 33-38 (1959).
Neutron Absorber Materials for Reactor Control, pp. 608-609, (1962).
Development of High Corrosion Resistance Zirconium-Base Alloys, Nov. 1990.

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