Preparation and Performance of Fully Ceramic Fuel Element Using Silicon Carbide as Coating Layers

Article Preview

Abstract:

Tristructural-isotropic (TRISO) coated fuel particles with spherical ceramic fuel kernels followed by three layers of pyrolytic carbon and one layer of silicon carbide (SiC) is successfully used in high temperature gas cooled reactor (HTGR) system. In this paper, an improved design concept of fully ceramic fuel is proposed. The kernels were coated by SiC layers with different densities. Two kinds of SiC coatings, namely porous SiC and dense SiC were prepared by a fluidized bed chemical vapor deposition method. The densities of porous SiC and dense SiC were 1.40 g/cm3 and 3.20 g/cm3, respectively. By controlling experimental parameters, densities of the SiC layer can be adjusted. The structure and micromorphology of the coated particles were investigated by various technologies such as XRD, SEM, and EDX. The coated particles were dispersed in SiC matrix and further sintered to dense compacts. High temperature oxidation test confirmed the robustness of the fuel elements.

You might also be interested in these eBooks

Info:

Periodical:

Pages:

835-840

Citation:

Online since:

July 2016

Export:

Price:

Permissions CCC:

Permissions PLS:

Сopyright:

© 2016 Trans Tech Publications Ltd. All Rights Reserved

Share:

Citation:

* - Corresponding Author

[1] W.J. Kim, D. Kim, J. Y. Park, Fabrication and material issues for the application of SiCcomposites to LWR fuel cladding, Nuclear Engineering and Technology 45(2013) 565-572.

DOI: 10.5516/net.07.2012.084

Google Scholar

[2] R. Liu, M. Liu, Z. Li, Y. Shao, B. Liu, Application of silicon carbide in nuclear fuel elements, Materials Review 29 (2015) 1-9.

Google Scholar

[3] M. Meyer, R. Fielding, J. Gan, Fuel development for gas-cooled fast reactors, Journal of Nuclear Materials, 371 (2007) 281-287.

DOI: 10.1016/j.jnucmat.2007.05.013

Google Scholar

[4] M. Liu, R. Liu, Z. Li, Y. Shao, B. Liu, Application of particuology in high temperature gas cooled nuclear reactor engineering, China Powder Science and Technology, 20 (2014) 1-7.

Google Scholar

[5] H. Nickel, H. Nabielek, G. Pott, A. W. Mehner, Long time experience with the development of HTR fuel elements in Germany, Nuclear Engineering and Design 217 (2002) 141-151.

DOI: 10.1016/s0029-5493(02)00128-0

Google Scholar

[6] M. Liu, R. Liu, B. Liu, Y. Shao, Preparation of the coated nuclear fuel particle using the fluidized bed-chemical vapor deposition (FB-CVD) method, Procedia Engineering 102 (2015) 1890-1895.

DOI: 10.1016/j.proeng.2015.01.328

Google Scholar

[7] D. A. Petti, J. Boungiorno, J. T. Maki, R. R. Hobbins, G. K. Miller, Key differences inthefabrication, irradiation and high temperature accident testing of US and German TRISO-coated particle fuel, and their implications on fuel performance, Nuclear Engineering and Design 222 (2003).

DOI: 10.1016/s0029-5493(03)00033-5

Google Scholar

[8] R. Liu, B. Liu, K. Zhang, M. Liu, Y. Shao, C. Tang, High temperature oxidation behavior of SiC coating in TRISO coated particles, Journal of Nuclear Materials 453 (2014) 107–114.

DOI: 10.1016/j.jnucmat.2014.06.055

Google Scholar

[9] Y. Choi, J. K. Lee, An analytical model for the Amoeba effect in UO2 fuel pellets, Journal of Nuclear Materials 357 (2006) 213-220.

DOI: 10.1016/j.jnucmat.2006.05.053

Google Scholar

[10] J. J. Powers, B. D. Wirth, A review of TRISO fuel performance models, Journal of Nuclear Materials 405 (2010) 74-82.

DOI: 10.1016/j.jnucmat.2010.07.030

Google Scholar

[11] R. Liu, M. Liu, J. Chang,Y. Shao, B. Liu. An improved design of TRISO particle with porous SiC inner layer by fluidized bed-chemical vapor deposition, Journal of Nuclear Materials467 (2015) 917-926.

DOI: 10.1016/j.jnucmat.2015.10.055

Google Scholar