Ceramic-ceramic composites and process therefor, nuclear fuels formed thereby, and nuclear reactor systems and processes operated therewith

Abstract

A process of producing ceramic-ceramic composites, including but not limited to nuclear fuels, and composites capable of exhibiting increased thermal conductivities. The process includes milling a first ceramic material to produce a powder of spheroidized particles of the first ceramic material, and then co-milling particles of a second ceramic material with the spheroidized particles of the first ceramic material to cause the particles of the second ceramic material to form a coating on the spheroidized particles of the first material. The spheroidized particles coated with the particles of the second ceramic material are then compacted and sintered to form the ceramic-ceramic composite, in which the second ceramic material forms a continuous phase completely surrounding the spheroidized particles of the first ceramic material.

Description

[0001] Cross References to Related Applications [0002] This application claims the benefit of US Provisional Patent No. 61 / 386 / 848 filed September 27, 2010, the contents of which are incorporated herein by reference. Background of the invention [0003] This invention relates generally to nuclear power generation materials, systems and processes, and more particularly to engineered uranium dioxide (UO 2 ) nuclear fuel to increase its thermal conductivity. [0004] Industrial light water reactors typically use pure or combustible poisoned doped uranium dioxide (UO 2 ) pellets as nuclear fuel. Although uranium dioxide has exhibited many desirable properties, it has a relatively low thermal conductivity, which causes large temperature gradients to develop across the fuel pellet. This temperature gradient and the resulting high center line temperature limits the operational performance of nuclear reactors due to overheating, melting, and various effects such as thermal stress...

AI Technical Summary

Problems solved by technology

Although uranium dioxide has exhibited many desirable properties, it has a relatively low thermal conductivity, which causes large temperature gradients to develop across the fuel pellet

This temperature gradient and the resulting high center line temperature limits the operational performance of nuclear reactors due to overheating, melting, and various effects such as thermal stresses that cause pellets to interact with the cladding and release fission products gas

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