Fabrication of Monolithic RERTR Fuels by Hot Isostatic Pressing

The Reduced Enrichment for Research and Test Reactors (RERTR) program develops advanced nuclear fuels for high-power test reactors. Monolithic fuel design provides higher uranium loading than that of the traditional dispersion fuel design. Hot isostatic pressing is a promising process for low-cost b...

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Bibliographic Details
Published inNuclear technology Vol. 172; no. 2; pp. 204 - 210
Main Authors Jue, Jan-Fong, Park, Blair H., Clark, Curtis R., Moore, Glenn A., Keiser, Dennis D.
Format Journal Article
LanguageEnglish
Published La Grange Park, IL Taylor & Francis 01.11.2010
American Nuclear Society
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Summary:The Reduced Enrichment for Research and Test Reactors (RERTR) program develops advanced nuclear fuels for high-power test reactors. Monolithic fuel design provides higher uranium loading than that of the traditional dispersion fuel design. Hot isostatic pressing is a promising process for low-cost batch fabrication of monolithic RERTR fuel plates for these high-power reactors. Bonding U-Mo fuel foil and 6061-Al cladding by hot isostatic press bonding was successfully developed at Idaho National Laboratory. Because of the relatively high processing temperature, the interaction between fuel meat and aluminum cladding is a concern. Two different methods were employed to mitigate this effect: a diffusion barrier and a doping addition to the interface. Both types of fuel plates have been fabricated by hot isostatic press bonding. Preliminary results show that the direct fuel/cladding interaction during the bonding process was eliminated by introducing a thin zirconium diffusion barrier layer between the fuel and the cladding. Fuel plates were also produced and characterized with a silicon-rich interlayer between fuel and cladding. This paper reports the recent progress of this developmental effort and identifies the areas that need further attention.
Bibliography:ObjectType-Article-2
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DE-AC07-05ID14517
INL/JOU-09-16617
DOE - NE
ISSN:0029-5450
1943-7471
1943-7471
DOI:10.13182/NT10-A10905