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Effect of $U_3O_8$-seed on the grain growth of uranium dioxide  

Rhee, Young-Woo (Advanced LWR Fuel Development Team, Korea Atomic Energy Research Institute)
Kim, Dong-Joo (Advanced LWR Fuel Development Team, Korea Atomic Energy Research Institute)
Kim, Keon-Sik (Advanced LWR Fuel Development Team, Korea Atomic Energy Research Institute)
Publication Information
Journal of the Korean Crystal Growth and Crystal Technology / v.17, no.2, 2007 , pp. 75-81 More about this Journal
Abstract
Densification and grain growth have been investigated in 5 wt% $U_3O_8$ seeded $UO_2$ and compared with those of the common $UO_2$ pellet. $UO_2$ compacts and $U_3O_8$ seeded $UO_2$ compacts were sintered at $1300{\sim}1700^{\circ}C$ for 0 h to 4 h. Density and grain size of the sintered pellets were measured by the water immersion method and the image analyzer, respectively. The seeded pellet has a slightly lower density during the intermediate sintering stage. However, the difference of density between two pellets decreases to about 0.5%TD with increasing the sintering temperature. The grain size of the two pellets is similar until $1600^{\circ}C$ but that of the seeded pellet rapidly increases with increasing the sintering temperature.
Keywords
Nuclear fuel; Uranium dioxide; Grain growth; Seed;
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1 A.H. Booth, 'A method of calculating fission gas diffusion from $UO_{2}$ fuel and its application to the X-2-f loop test', Atomic Energy of Canada Limited, AECL-496 (1957)
2 J.A. Turnbull, 'The effect of grain size on the swelling and gas release properties of $UO_{2}$ during irradiation', J. Nucl. Mater. 50 (1974) 62   DOI   ScienceOn
3 I. Amato, R.L. Colombo and A.P. Balzari, 'Grain growth in pure and titania-doped uranium dioxide', J. Nucl. Mater. 18 (1966) 252   DOI   ScienceOn
4 F. Valdivieso, V. Francon, F. Byasson, M. Pijolat, A. Feugier and V. Peres, 'Oxidation behaviour of unirradiated sintered $UO_{2}$ pellets and powder at different oxygen partial pressures, above $350^{\circ}C$', J. Nucl. Mater. 354 (2006) 85   DOI
5 J.E. Burke and D. Turnbull, 'Recrystallization and grain growth', Progress in Metal Physics 3 (1952) 220   DOI   ScienceOn
6 J.B. Ainscough, L.F.A. Raven and P.T. Sawbridge, 'Fission gas retentive $UO_{2}$ fuels', pp. 53 in Fabrication of Water Reactor Fuel Elements, lAEA-SM-233/16 (1979)
7 K.W Song, K.S. Kim, K.W Kang and Y.H. Jung, 'Fabrication of large-grained $UO_{2}$ pellets by the addition of $U_{3}O_{8}$ seeds', J. Nucl. Sci. Technol. Supplement 3 (2002) 838
8 K.C. Radford and J.M. Pope, '$UO_{2}$ fuel pellet microstructure modification through impurity additions', J. Nucl. Mater. 116 (1983) 305   DOI
9 J.W Cahn, 'The impurity-drag effect in grain boundary motion', Acta Metall. 10 (1962) 789   DOI   ScienceOn
10 K.W. Song, S.H. Kim, B.G. Kim,Y.W. Lee, M.S. Yang and H.S. Park, 'Microstructure development during sintering of $Nb_{2}O_{5}$ - doped $UO_{2}$ pellets under $H_{2}$ and $CO_{2}$atmospheres', J. Kor. Nucl. Soc. 26 (1994) 484
11 H. Assmann, W. Doerr, G. Gradel, G. Maier and M. Peehs, 'Doping $UO_{2}$ with niobia -- Beneficial or not?', J. Nucl. Mater. 98 (1981) 216
12 K.W Song, K.S. Kim, K.W Kang and Y.H. Jung, 'Grain size control of $UO_{2}$ pellets by adding heattreated $U_{3}O_{8}$ particles to $UO_{2}$ powder', J. Nucl. Mater. 317 (2003) 204   DOI
13 S.J.L. Kang and D.N. Yoon, 'Method for analysing the experimental data of ostwald ripening', J. Mater. Sci. Lett. 2 (1983) 291   DOI   ScienceOn
14 H. Matzke, 'On uranium self-diffusion in $UO_{2}$ and $UO_{2+x}$', J. Nucl. Mater. 30 (1969) 26   DOI   ScienceOn
15 W.D. Kingery and B. Francois, 'Grain growth in porous compacts', J. Am. Ceram. Soc. 48 (1965) 546   DOI
16 K.W Song, K.S. Kim and Y.H. Jung, 'Densification behavior of $U_{3}O_{8}$ powder compacts by dilatometry', J. Nucl. Mater. 279 (2000) 356   DOI   ScienceOn
17 K.W Lay, 'Grain growth in $UO_{2}-Al_{2}O_{3}$ in the presence ofa liquid phase', J. Am. Ceram. Soc. 51 (1968) 373
18 J.B. Ainscough, F. Rigby and S.C. Osborn, 'The effect of titania on grain growth and densification of sintered $UO_{2}$', J. Nucl. Mater. 52 (1974) 191   DOI   ScienceOn