Pu-ZR Alloy high-temperature activation-measurement foil

Details Pu-ZR Alloy high-temperature activation-measurement foil Pu-ZR Alloy high-temperature activation-measurement foil

1976-10-26

1977-08-02

Schafer, Richard E.

Radiant energy

Ionic separation or analysis

Static field-type ion path-bending selecting means

751227, 176 19R, 176 89, 250390, G21C 302, G01T 300

Patent

active

040393780

ABSTRACT:
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.

REFERENCES:
patent: 2950967 (1960-08-01), Schonfeld et al.
patent: 3004906 (1961-10-01), Binstock
patent: 3072475 (1963-01-01), Baker et al.
patent: 3600585 (1971-08-01), Kelly et al.
Marples, J. A. C. "The Lattice Parameters of Some .delta.- and .epsilon.- Plutoniun Alloys," In J. Phys. Chem. Solids. 25: pp. 521-534, 1964.
Harvey, M. R. et al. "Chemical Diffusivities of Delta Stabilized Pu-Zr Alloys," Trans ASM, 62: 1014-1015, 1969.
Marples, J. A. C. "The Plutonium-Zirconium Phase Diagram," In J. Less Com. Met. 1960.

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