Postirradiation Examination of a Low Enriched U3Si2-Al Fuel Element Manufactured and Irradiated at Batan, Indonesia
Postirradiation Examination of a Low Enriched U3Si2-Al Fuel Element Manufactured and Irradiated at Batan, Indonesia

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Published: 1994

Total Pages: 9

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The first low-enriched U3Si2-Al dispersion plate-type fuel element produced at the Nuclear Fuel Element Center, BATAN, Indonesia, was irradiated to a peak 235U burnup of 62%. Postirradiation examinations performed to data shows the irradiation behavior of this element to be similar to that of U3Si2-Al plate-type fuel produced and tested at other institutions. The main effect of irradiation on the fuel plates is a thickness increase of 30--40 [mu]m (2.5-3.0%). This thickness increase is almost entirely due to the formation of a corrosion layer (Boehmite). The contribution of fuel swelling to the thickness increase is rather small (less than 10 [mu]m) commensurate with the burnup of the fuel and the relatively moderate as-fabricated fuel volume fraction of 27% in the fuel meat.

Energy Research Abstracts
Energy Research Abstracts

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Published: 1995

Total Pages: 598

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Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.

The Use of U3Si2 Dispersed in Aluminum in Plate-type Fuel Elements for Research and Test Reactors
The Use of U3Si2 Dispersed in Aluminum in Plate-type Fuel Elements for Research and Test Reactors

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Published: 1987

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A high-density fuel based on U3Si2 dispersed in aluminum has been developed and tested for use in converting plate-type research and test reactors from the use of highly enriched uranium to the use of low-enriched uranium. Results of preirradiation testing and the irradiation and postirradiation examination of miniature fuel plates and full-sized fuel elements are summarized. Swelling of the U3Si2 fuel particles is a linear function of the fission density in the particle to well beyond the fission density achievable in low-enriched fuels. U3Si2 particle swelling rate is approximately the same as that of the commonly used UAl(subscript x) fuel particle. The presence of minor amounts of U3Si or uranium solid solution in the fuel result in greater, but still acceptable, fuel swelling. Blister threshold temperatures are at least as high as those of currently used fuels. An exothermic reaction occurs near the aluminum melting temperature, but the measured energy releases were low enough not to substantially worsen the consequences of an accident. U3Si2-aluminum dispersion fuel with uranium densities up to at least 4.8 Mg/m3 is a suitable LEU fuel for typical plate-type research and test reactors. 42 refs., 28 figs., 7 tabs.

Postirradiation Examination of High-U-loaded Low-enriched U3O, UAl2, and U3Si Test Fuel Plates
Postirradiation Examination of High-U-loaded Low-enriched U3O, UAl2, and U3Si Test Fuel Plates

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Published: 1984

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The scope of this work is to present an evaluation of the postirradiation examination of the second set of high-U-loaded low-enriched U3O, UAl2 and U3Si miniature plates manufactured by the Comision Nacional de Energia Atomica (CNEA) of Argentina, and irradiated and examinated, within the framework of the Reduced Enrichment Research and Test Reactor (RERTR) Program, at Oak Ridge National Laboratory and Argonne National Laboratory. This paper includes fabrication details of the plates, their irradiation history and the results of postirradiation examination which are compared to those of the previous test and to present results from other laboratories participating in the RERTR Program. Postirradiation examination of these plates showed satisfactory poerformance for the oxides, aluminides and silicides (except for the highest-loaded U3Si plate) with the only indication of detrimental behavior during the slight bowing of some plates at about 80% burnup.