Method for homogenizing mixed oxide nuclear fuels

Plastic and nonmetallic article shaping or treating: processes – Shaping or treating radioactive material

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G21C 2100

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active

042619343

ABSTRACT:
A method for homogenizing plutonia particles in mixed oxide nuclear reactor fuels. The method includes the step of blending urania particles and plutonia particles together and pressing the mixture into a pellet. The pellet is thereafter sintered in a reducing atmosphere with hydrogen present so that pores are formed in the pellet. The plutonia particles are thereby transformed into spherical shells of dense PuO.sub.2-x that surround each pore and which homogenizes the fuel.

REFERENCES:
patent: 3689428 (1972-09-01), Pechin et al.
patent: 3995000 (1976-11-01), Butler et al.
"The Homogenization of ThO.sub.2 -UO.sub.2 " (LWBR Development Program) by R. M. Berman, AEC Research and Development Report, WAPD-TM-1051, Dec. 1972.
R. Thiesen and D. Vollath, "Plutonium Distribution and Diffusion in UO.sub.2 -PuO.sub.2 Ceramics", Proceedings of Symposium on the Use of Plutonium as a Reactor Fuel, International Atomic Energy Agency, Brussels, Mar. 13-17, 1967. Pub. International Atomic Agency, Vienna, 1967, pp. 253-264.
H. Andriessen et al. "Fabrication de Combustibles a Oxydes Mixtures UO.sub.2 -PuO.sub.2 pour Reacteurs a Neutrons Rapides", ibid, p. 237.
R. E. Woodley, "Variation in the Oxygen Potential of a Mixed-Oxide with Simulated Burnup", Journal of Nuclear Materials 74 (1978) 290-296.
P. E. Hart and D. R. Olander, "Plutonia Particle Behavior during the Sintering of Mixed Oxide Fuels", Journal of Nuclear Materials 78 (1978) 315-325.

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