Development of oxide dispersion strengthened ferritic steels with and without aluminum
Received date: 14 Nov 2011
Accepted date: 29 Dec 2011
Published date: 05 Mar 2012
Copyright
Pure Fe, Cr, Al, Ti elemental powders and pre-alloyed Y2O3 powder were processed by high energy mechanical milling. The compositions of the mixed powders are designed as Fe-18Cr-0.2Ti-0.35Y2O3 and Fe-18Cr-5Al-0.2Ti-0.35Y2O3 in weight percent. The as-milled powders were consolidated by hot extrusion at 1423 K. The dispersed oxide particles were identified to be titania+ yttria for Al-free oxide dispersion strengthened (ODS) steel and alumina+ yttria for Al-added ODS steel, respectively. The ultimate tensile strength of Al-free ODS steel was higher than that of Al-added ODS steel over the temperature range of 298–973 K, because of the difference in number density and size of thermally stable oxide particles dispersed in both steel matrices. The strength in the longitudinal direction was lower than that in the transverse direction, probably due to anisotropy of the microstructure with elongated grains in the hot-extrusion direction for the 18%Cr-ODS steels with and without 5%Al.
Key words: oxide dispersion strengthened (ODS) steel; milling; extrusion; aluminum; yttria
Jae Hoon LEE . Development of oxide dispersion strengthened ferritic steels with and without aluminum[J]. Frontiers in Energy, 2012 , 6(1) : 29 -34 . DOI: 10.1007/s11708-012-0178-x
1 |
Lee J H, Kasada R, Cho H S, Kimura A. Irradiation-induced hardening and embrittlement of high-Cr ODS ferritic steels. Journal of ASTM International, 2009, 6(8): Paper ID JAI101952
|
2 |
Lee J H, Kasada R, Kimura A, Okuda T, Inoue M, Ukai S, Ohnuki S, Fujisawa T, Abe F. Influence of alloy composition and temperature on corrosion behavior of ODS ferritic steels. Journal of Nuclear Materials, 2011, 417(1-3): 1225-1228
|
3 |
Kimura A, Kasada R, Iwata N, Kishimoto H, Zhang C H, Isselin J, Dou P, Lee J H, Muthukumar N, Okuda T, Inoue M, Ukai S, Ohnuki S, Fujisawa T, Abe F. Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems. Journal of Nuclear Materials, 2011, 417(1-3): 176-179
|
4 |
Kasada R, Lee S G, Isselin J, Lee J H, Omura T, Kimura A, Okuda T, Inoue M, Ukai S, Ohnuki S, Fujisawa T, Abe F. Anisotropy in tensile and ductile-brittle transition behavior of ODS ferritic steels. Journal of Nuclear Materials, 2011, 417(1-3): 180-184
|
5 |
Lee J H. Microstructure and strengthening mechanisms of oxide dispersion strengthened ferritic alloy. Applied Mechanics and Materials, 2011, 87: 243-248
|
6 |
Kaneko J, Sugamata M, Blaz L, Kamei R. Aluminum-low melting metal alloys prepared by mechanical alloying with addition of oxide. Key Engineering Materials, 2000, 188: 73-82
|
7 |
Blaz L, Kaneko J, Sugamata M. Microstructural evolution in mechanically alloyed Al-heavy-metal oxide composites. Materials Chemistry and Physics, 2003, 81(2,3): 387-389
|
8 |
Lee J H. Positron annihilation characterization of Fe-Y2O3 composite powder after mechanical alloying and heat treatment. Journal of Nanoscience and Nanotechnology, 2012 (in Press)
|
9 |
Ukai S, Harada M, Okada H, Inoue M, Nomura S, Shikakura S, Asabe K, Nishida T, Fujiwara M. Alloying design of oxide dispersion strengthened ferritic steel for long life FBRs core materials. Journal of Nuclear Materials, 1993, 204(1): 65-73
|
10 |
Capdevila C, Chen Y L, Jones A R, Bhadeshia H K D H. Grain boundary mobility in Fe-base oxide dispersion strengthened PM2000 alloy. ISIJ International, 2003, 43(5): 777-783
|
11 |
Okuda T, Fujiwara M. Dispersion behaviour of oxide particles in mechanically alloyed ODS steel. Journal of Materials Science Letters, 1995, 14(22): 1600-1603
|
12 |
Krautwasser P, Czyrska-Filemonowicz A, Widera M, Carsughi F.Thermal stability of dispersoids in ferritic oxide-dispersion-strengthened alloys. Materials Science and Engineering, 1994, A177(1,2): 199-208
|
13 |
Oksiuta Z, Olier P, de Carlan Y, Baluc N. Development and characterisation of a new ODS ferritic steel for fusion reactor application. Journal of Nuclear Materials, 2009, 393(1): 114-119
|
14 |
Romanoski G R, Snead L L, Klueh R L, Hoelzer D T. Development of an oxide dispersion strengthened, reduced-activation steel for fusion energy. Journal of Nuclear Materials, 2000, 283-287(1): 642-646
|
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