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Published: 2016-09-30
Abstract Views: 115
Views PDF: 52
DOI: https://doi.org/10.53747/jnst.v6i3.168
Issue
Vol. 6 No. 3 (2016)
Section
Articles
How to Cite
Nguyen , T. H., & Le, B. T. (2016). The Brandon mathematical model describing the effect of calcination and reduction parameters on specific surface area of ex-ADU UO₂ powders . Nuclear Science and Technology, 6(3), 54-59. https://doi.org/10.53747/jnst.v6i3.168

The Brandon mathematical model describing the effect of calcination and reduction parameters on specific surface area of ex-ADU UO₂ powders

Nguyen Trong Hung1, Le Ba Thuan1
1 Institute for Technology of Radioactive and Rare Elements (ITRRE), 48 Lang Ha, Dong Da, Ha Noi, Vietnam

Main Article Content

Abstract

The report “Brandon mathematical model describing the effect of calcination and reduction parameters on specific surface area of UO2 powders” [14] has built up a mathematical model describing the effect of the fabrication parameters on SSA (Specific Surface Area) of ex-AUC (Ammonium Uranyl Carbonate) UO2 powders. In the paper, the Brandon mathematical model that describe the relationship between the essential fabrication parameters [reduction temperature (TR), calcination temperature (TC), calcination time (tC) and reduction time (tR)] and SSA of the obtained ex-ADU (Ammonium Di-Uranate) UO2 powder product has established. The proposed model was tested with Wilcoxon’s rank sum test, showing a good agreement with the experimental parameters. The proposed model can be used to predict and control the SSA of ex-ADU UO2 powders

Article Details

Keywords

UO₂ powder, Ammonium Di-Uranate (ADU), Brandon mathematical model

References

1. Ronald A. Knief, “Nuclear Engineering: Theory and Technology of Commercial Nuclear Power”, Hemisphere Publishing Corporation, 1992.
2. D. Olander, “Nuclear fuels – Present and future”, J. Nucl. Mater., 389, 1–22, 2009.
3. Nuclear Fuel Cycle Information System, “A Directory of Nuclear Fuel Cycle Facilities”, IAEA-TECDOC-1613, 2009 Edition.
4. M. C. Lee, C. J. Wu, “Conversion of UF6 to UO2: A quasi-optimization of the ammonium uranyl carbonate process” J. Nucl. Mater., 185,190-201, 1991.
5. Ching-Tsven Huang, “Dry-ADU process for UO2 production”, J. Nucl. Mater., 199, 61-67, 1992.
6. Birsen Ayaz, et. al., “The possible usage of ex-ADU uranium dioxide fuel pellets with low-temperature sintering”, J. Nucl. Mater., 280, 45-50, 2000.
7. H. Assmann, “Microstructure and Density of UO2 for Light Water Reactors as Related to Powder Properties”, Ceramic Powders, Amsterdam , 707 – 7117, 1983.
8. P. Balakrishna, C. K. Asnani, “Uranium Dioxide Powder Preparation, Pressing, and Sintering for optimum Yield”, Nuclear Technology, 127, 375 – 381, 1999.
9. Y. W. Lee and M. S.Yang, “Characterization of HWR fuel pellets fabricated using UO2 powders from different conversion processes”, J. Nucl. Mater., 178, 217-226, 1991.
10. N. Lindman, “The kinetics of the elimination of fluorine from uranyl fluoride/uranium dioxide pellets”, J. Nucl. Mater., 66, 23-36, 1977.
11. Z. X. Song, X. W. Huang, “Defluorination Behavior and Mechanism of Uranium Dioxide”, J. of Radioanalytical and Nucl. Chemistry, 237, 81-84, 1998.
12. V. V. Kafarov, Cybernetic methods in chemistry and chemical engineering, second ed., Moscow, [in Russian], 1971.
13. A. A. Melnikov, G. S. Kozlova, V. L. Gunar, N.Y. Smirnov, and V. V. Zarutskii, “Study of the solubility of L (+)-threoammonium salt of L-pantoic acid in the water-sodium chloride-sodium D-pantoate system”, Pharmaceutical Chemistry Journal, 15, 666-668, 1981.
14. Nguyen Trong Hung, Le Ba Thuan, et. al., “Brandon mathematical model describing the effect of calcination and reduction parameters on specific surface area of UO2 powders”, J. Nucl. Mater., 474, 150-154, 2016.