Development of an oxide dispersion strengthened, reduced-activation steel for fusion energy
Source abstract
Abstract
A reduced-activation steel having a nominal chemical composition of Fe, 9% Cr, 2% W, 0.25% V, 0.1% Ta, and 0.1% C was mechanically alloyed with a fine dispersion of Y2O3 and TiO2 to assess the potential for extending the elevated temperature limit of this alloy for structural applications. The total oxide dispersion content was varied from 0.25% to 1% and the molar ratio, TiO2/Y2O3 from 0 to 2. An argon atomized 9Cr2WVTa steel powder was ball milled under vacuum, extruded at 1150°C to a 16 to 1 reduction in area, followed by a normalize and age heat treatment. Mechanical properties were assessed by elevated temperature tensile tests over the temperature range from room temperature to 800°C. Transmission electron microscopy revealed a favorable dispersion of the oxide particles. Oxide dispersion strengthening by mechanical alloying resulted in significant improvement in elevated temperature tensile strengths. Extended ball-milling times improved oxide dispersion, microstructural refinement, and mechanical properties.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Microstructure and Mechanical Properties of Steels · Metal and Thin Film Mechanics
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (14)
Show source-provided references
1. Klueh · J. Nucl. Mater. · 1992 · 191–194 · 116
2. Hishinuma · J. Nucl. Mater. · 1998 · 253–258 · 19310.1016/S0022-3115(98)00395-X ↗
3. M. Lippens, K. Ehrlich, V. Levy, C. Brown, A. Calza Bini, in: Proceedings of the International Conference on Materials for Nuclear Core Applications, vol. 1, BNES, London, 1987, p. 177
4. J.J. Huet, L. Coheur, L. De Wilde, J. Gedopt, W. Hendrix, W. Vandermeulen, in: J.W. Davis, D.J. Michel (Eds.), Proceedings of the Topical Conference on Ferritic Alloys for Use in Nuclear Energy Technologies, Met. Soc. AIME, Warrendale, PA, 1984, p. 329
5. Huet · Nucl. Technol. · 1985 · 70 · 21510.13182/NT85-A33645 ↗
6. L. De Wilde, J. Gedopt, S. De Burbure, A. Delbrassine, C. Driesen, B. Kazimierzak, in: Proceedings of the International Conference on Materials for Nuclear Core Applications, BNES, London, 1987, p. 271
7. A. Alamo, J. Decours, M. Pigoury, C. Foucher, in: Proceedings of the International Conference on Structural Applications of Machanical Alloying, American Society for Metals, Materials Park, OH, 1990, p. 89
8. S.D. Antolovich, R.W. Stusrud, R.A. Mackay, D.L. Anton, T. Khan, R.D. Kissinger, D.L. Klarstrom (Eds.), Superalloys 92, The Minerals, Metals, Materials Society, Warrendale, PA, 1992
9. Alamo · Adv. Powder Metallurgy Particulate Mater. · 1992 · 7 · 169
10. Ukai · Trans. ANS · 1992 · 66 · 186
11. D.M. Jaeger, A.R. Jones, in: D. Coutsouradis, J.H. Davidson, J. Ewald, P. Greenfield, T. Khan, M. Malik, D.B. Meadowcroft, V. Regis, R.B. Scarlin, F. Schubert, D.V. Thorton (Eds.), Proceedings of the Conference on Materials for Advanced Power Engineering – Part II, Kluwer Academic, Dordrecht, 1994, p. 1507
12. Ukai · J. Nucl. Mater. · 1993 · 204 · 6510.1016/0022-3115(93)90200-I ↗
13. Ukai · J. Nucl. Sci. Technol. · 1998 · 35 · 29410.1080/18811248.1998.9733859 ↗
14. S. Ukai, T. Nishida, H. Okada, M. Inoue, T. Okuda, M. Fujiwara, K. Asabe, in: Proceedings of the International Symposium on Material Chemistry in Nuclear Environment, Tsukuba, Japan, 14 & 15 March 1996, p. 891