Radiation resistance and thermal creep of ODS ferritic steels
Source abstract
Abstract
Abstract Oxide dispersion strengthened (ODS) ferritic steels containing 0.38–0.39 wt% Y2O3 have been produced by mechanical alloying. After thermo-mechanical treatment, the structure of ODS steels includes polygonized extended grains and a great number (to ∼ 10 16 –10 17 cm −3 ) of ultrafine complex yttrium oxides ∼2–3 nm in diameter. Irradiation by fast neutrons to 4.5×10 26 n / m 2 (340 K) and 1.5×10 22 n / m 2 (77 K) leads to strengthening and plasticity decreasing in ODS alloys. The advantages of ODS ferritic steels in creep resistance and strength against ferritic-martensitic steel 12Cr–2Mo–Nb–B–V and austenitic steel 16Cr–15Ni–3Mo–Ti–V display obviously when creep rate is approximately 10 −2 h −1 and fracture time is longer than 1000 h.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Metal and Thin Film Mechanics
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References (11)
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1. Huet · 1984 · 197
2. L. Dewilde, J. Gedopt, A. Delbrassine, C. Driesen, B. Kazimierzak, in: Proceedings of the International Conference of Materials for Nuclear Reactor Core Application, Bristol, 1987, p. 271
3. T. Yun, S. Bingquan, P. Qingchun et al., in: Proceeings of Materials for Advanced Energy Systems and Fission and Fusion Engineering, Southwestern Institute of Physics, Chengdu, China, 1995, p. 110
4. Ukai · J. Nucl. Mater. · 1993 · 204 · 6510.1016/0022-3115(93)90200-I ↗
5. A.M. Wilson, M. C. Clayden, J. Standring, in: Proceedings of the International Conference of Materials for Nuclear Reactor Core Application, Bristol, 1987, p. 25
6. Asano · J. Nucl. Mater. · 1988 · 155–157 · 92810.1016/0022-3115(88)90443-6 ↗
7. Garner · Nucl. Mater. Frost B.R.T.Ed. Sci. Technol. · 1993 · 6 · 419
8. Gelless · Mater. Res. Soc. Symp. Proc. · 1995 · 373 · 112
9. Fusion Reactor Materials VIII. Proceedings of eighth International Conference on Fusion Reactor Mater. Part B. Ferritic steels. 6.1 (1998) 1143
10. Sagaradze · Fus. Eng. Design · 1998 · 9710.1016/S0920-3796(98)00219-1 ↗
11. Mukhopadhyay · J. Nucl. Mater. · 1998 · 258–263 · 120910.1016/S0022-3115(98)00188-3 ↗