The Study of Pre-Oxidation and Low Temperature Sintering Mechanism to Uo2+x Pellets

Article Preview

Abstract:

Uranium dioxide powders were surface pre-oxidation treated. Phases and properties of the powders after pre-oxidation treatment were investigated by DSC-TG、XRD、BET and Dilatometer. The results show that there is a little of U3O7 in uranium dioxide powders by pre-oxidation treatment at 240°C for 8h in air, UO2 powders will transform into U3O8 at 382°C for 8h in air. The shrinkage temperature of the uranium dioxide pellets after pre-oxidation treatment decreased from 1200°C to 580°C, densification rate (ΔL/L) increased also from 1.52×10-4/K to 3.08×10-4/K. The mechanism of low temperature sintering to pre-oxidation UO2+x pellets was explained by simplified point defect model and densification equation. The UO2+x diffusion coefficient, , is much higher than which of UO2. The densification equation is expressed by , and the factor A is according to , a=16.23658, b=0.04247 and c=-2.18802×10-5.

You might also be interested in these eBooks

Info:

Periodical:

Pages:

80-86

Citation:

Online since:

October 2014

Authors:

Export:

Price:

Permissions CCC:

Permissions PLS:

Сopyright:

© 2014 Trans Tech Publications Ltd. All Rights Reserved

Share:

Citation:

[1] B Ayaz, A N Bilge, The possible usage of ex-ADU uranium dioxide fuel pellets with low-temperature sintering , Journal of Nuclear Materials, , 280(2000)45-50.

DOI: 10.1016/s0022-3115(00)00033-7

Google Scholar

[2] Y Harada, UO2 sintering in controlled oxygen atmospheres of three-stage process, Journal of Nuclear Materials, 245(1997)217-223.

DOI: 10.1016/s0022-3115(96)00755-6

Google Scholar

[3] J C Gao, R Li, F W Zhong, X D Yang, Y Wang, Progress in processes of uranium dioxides pellets, Journal of Functional Materials, 37(2006)849-852.

Google Scholar

[4] H Chevrel, P Dehaudt, B francois, J F Baumard, Influence of surface phenomena during sintering of over stoichiometric uranium dioxide UO2+x, Journal of Nuclear Materials, 189(1992)175-182.

DOI: 10.1016/0022-3115(92)90530-x

Google Scholar

[5] K W Song, S H Kim, S H Na, Y W Lee, Effect of Nb2O3 addition on grain growth and densification in UO2 pellets under reducing and /or oxidizing atmospheres, Journal of Nuclear Materials, 209(1994)280-285.

DOI: 10.1016/0022-3115(94)90264-x

Google Scholar

[6] X D Yang, J C Gao, Y Wang, X Chang, Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere, Transactions of Nonferrous Metals society of China, 18(2008)171-177.

DOI: 10.1016/s1003-6326(08)60031-x

Google Scholar

[7] J C Gao, X D Yang, R Li, Low-temperature sintering mechanism on uranium dioxide, Journal of Materials Science, 42(2007)5936-5940.

DOI: 10.1007/s10853-007-1774-8

Google Scholar

[8] S H Kim, B G Kim, Proceedings of the workshop on manufacturing technology and process for reactor fuels, Tokai, Japan, (1996).

Google Scholar

[9] G P Han, Characteristic of the UO2 powders and pellets in PWR by France ADU process, Engineering and Technology on Nuclear Power, 25(2001)23-27.

Google Scholar

[10] R Li, J C Gao, X D Yang, X Chang, Establishment and Application of Point Defect Model to Uranium Dioxide, Atomic Energy Science and Technology, 43(2009)877-880.

Google Scholar

[11] R Li, Active mechanism of low-temperature sintering to UO2+x pellets, Journal of Functional Materials, 43(Aug. Suppl, 2012)43-46.

Google Scholar

[12] W D Kingery, M Berg, Study of the Initial Stages of Sintering Solids by Viscous Flow, Evaporation-Condensation, and Self-Diffusion, Journal of Applied Physics, 26(1955)1205-1212.

DOI: 10.1063/1.1721874

Google Scholar