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

A technology of ceramic composite materials and ceramic materials, applied in the field of nuclear power generation materials, can solve problems such as low thermal conductivity and large temperature gradient, achieve high thermal conductivity, increase thermal conductivity, and improve the effect of fission gas retention

Inactive Publication Date: 2013-09-11
PURDUE RES FOUND INC
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  • Summary
  • Abstract
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  • Claims
  • Application Information

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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 hi...

Method used

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

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Embodiment Construction

[0023] The present invention provides an advance in the science and technology of preparing ceramic nuclear fuels with higher thermal conductivity. As will be discussed below, the present invention includes methods for preparing heterogeneous ceramic-ceramic nuclear fuels especially based on UO 2 A nuclear fuel process where BeO is the added ceramic phase, which increases the effective thermal conductivity of the nuclear fuel. A preferred aspect of the invention uses a three-dimensional (3-D) finite element method (FEM) to thermally model the fuel, by which thermal conductivity can be predicted as a guide for subsequent process optimization. Other preferred aspects of the invention include the actual production process for producing ceramic-ceramic fuel pellets by which the microstructure of the fuel produced has a controlled particle size distribution and a controlled volume fraction for the different ceramic phases. The pressing and sintering parameters used in the preparat...

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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...

Claims

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Application Information

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IPC IPC(8): G21F1/06
CPCC04B35/51C04B35/6261C04B38/00C04B2111/00862C04B2235/3205G21C3/64G21C21/02Y02E30/30C04B38/0058G21F1/06
Inventor A.A.索罗蒙H.S.库基博特拉S.T.雷文卡S.M.麦迪维特J.C.拉古萨
Owner PURDUE RES FOUND INC
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