Title of article
Literature review of thermal and radiation performance parameters for high-temperature, uranium dioxide fueled cermet materials
Author/Authors
Haertling، نويسنده , , C. and Hanrahan Jr.، نويسنده , , R.J.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2007
Pages
19
From page
317
To page
335
Abstract
High-temperature fissile-fueled cermet literature was reviewed. Data are presented primarily for the W–UO2 as this was the system most frequently studied; other reviewed systems include cermets with Mo, Re, or alloys as a matrix. Failure mechanisms for the cermets are typically degradation of mechanical integrity and loss of fuel. Mechanical failure can occur through stresses produced from dissimilar expansion coefficients, voids created from diffusion of dissimilar materials or formation of metal hydride and subsequent volume expansion. Fuel loss failure can occur by high temperature surface vaporization or by vaporization after loss of mechanical integrity. Techniques found to aid in retaining fuel include the use of coatings around UO2 fuel particles, use of oxide stabilizers in the UO2, minimizing grain sizes in the metal matrix, minimizing impurities, controlling the cermet sintering atmosphere, and cladding around the cermet.
Journal title
Journal of Nuclear Materials
Serial Year
2007
Journal title
Journal of Nuclear Materials
Record number
1365318
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