Pu-ZR Alloy high-temperature activation-measurement foil

Patent · Tue Aug 02 04:00:00 EDT 1977

OSTI ID:862895

McCuaig, Franklin D ^[1]

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1. Westmont, IL

A nuclear reactor fuel alloy consists essentially of from slightly greater than 7 to about 4 w/o zirconium, balance plutonium, and is characterized in that the alloy is castable and is rollable to thin foils. A preferred embodiment of about 7 w/o zirconium, balance plutonium, has a melting point substantially above the melting point of plutonium, is rollable to foils as thin as 0.0005 inch thick, and is compatible with cladding material when repeatedly cycled to temperatures above 650.degree. C. Neutron flux densities across a reactor core can be determined with a high-temperature activation-measurement foil which consists of a fuel alloy foil core sandwiched and sealed between two cladding material jackets, the fuel alloy foil core being a 7 w/o zirconium, plutonium foil which is from 0.005 to 0.0005 inch thick.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL
• Assignee: United States of America as represented by United States Energy (Washington, DC)
• Patent Number(s): US 4039378
• Application Number: 05/735,566
• OSTI ID: 862895
• Country of Publication: United States
• Language: English

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