Mechanical Alloying and Properties of ODS Ferritic Steels

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Abstract:

Oxide-dispersion strengthened (ODS) ferritic stainless steels have been considered as promising high-temperature materials such as interconnects for oxide-fuel cells and nuclear materials for Liquid Metal Fast Reactors or Super-Critical-Water-Cooled Reactors. In the present work, we have prepared Fe-14Cr-2Al-1Si-0.3Ta-1Y2O3 ferritic stainless steels which were dispersion-strengthened by nano-sized Y2O3 via mechanical alloying of elemental powder mixtures and subsequent hot consolidation. A comparison was made with MA 957 and DY-01 alloys. The mechanically alloying behaviour and consolidated mechanical properties of the Fe-14Cr-2Al-1Si- 0.3Ta-1Y2O3 ferritic steels were strongly influenced by processing parameters, especially milling atmosphere. The stability of yttrium oxides and oxidation resistance at high temperatures were examined. The preliminary result shows that the mechanically alloyed Fe-14Cr-2Al-1Si-0.3Ta- 1Y2O3 ferritic stainless steel exhibits interesting properties to be exploited as high temperature materials.

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Advanced Materials Research (Volumes 15-17)

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696-701

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February 2006

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© 2007 Trans Tech Publications Ltd. All Rights Reserved

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[1] Harumi Yokokawa, Natsuko Sakai, Teruhisa Horita and Katsuhiko Yamaji, Fuel Celles, 1, No. 2 (2001) 117.

Google Scholar

[2] S. Elangovan, Shekar Balagopal, and Insoo Bay, J. of Materials Engineering and Performance, Vol. 13, No. 3, (2004) 6.

Google Scholar

[3] M.L. Hamilton, D.S. Gelles, PNLL-13168 (2000).

Google Scholar

[4] D. J. Edwards, E. P. Simonen and S. M. Bruemmer, J. Nucl. Materials, 317 (2003) 13.

Google Scholar

[5] D. J. Edwards, E. P. Simonen, F. A. Garner, B. A. Oliver and S. M. Bruemmer, J. Nucl. Materials, 317 (2003) 32.

Google Scholar

[6] S. Ukai, M. Harada, H. Okada, M. Inoue, S. Nomura, S. Suikakura, K. Asabe, M. Fujiwara, J. Nucl. Mater., 204 (1993) 65.

Google Scholar

[7] J. J. Fischer, U.S. Patent 4, 075, 010 issued Feb 21, (1978).

Google Scholar

[8] A. Alamo, J. Decours, M. Pigoury, C. Foucher, Proc. ASM Int. on Structural Application of Mechanical Alloying, Mar. 27-29, (1990) 89.

Google Scholar

[9] S. Ukai, T. Nishisa, H. Okada, T. Okuda, M. Fujiwara, K. Asabe, J. Nucl. Sci. Technol., 34 (3) (1997) 256.

Google Scholar

[10] J.J. Huet, Ch. Lecompte, Proc. Int. Conf. On Ferritic Steels for High Temp. Appl., Ed. A.K. Khare, ASM (1983) 210.

Google Scholar

[11] L. De Wild, J. Gedopt, S. de Burbure, A. Delbrassine, C. Driesen, B. Kazimierzak, Proc. Int. Conf. On Material for Nucl. Reactor Core Appl., BNES, London (1987) 271.

Google Scholar