T. Stasiak , J.J. Jasiński , M. Zieliński , M. Wilczopolska , A. Kosińska , W. Chmurzyński , K. Mulewska , R. Diduszko , M. Chmielewski , M. Kowal , J. Rzempołuch , K. Ciporska , Ł. Kurpaska , J. Jagielski
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引用次数: 0
Abstract
FeCrAl-based ODS alloys are promising for Generation IV nuclear reactor components since they present remarkable properties, such as high mechanical strength and good irradiation resistance. However, there is still relatively little information on the impact of minor alloying elements, e.g., Ti or V, and manufacturing conditions on the properties of these alloys. In this paper, two FeCrAl-based alloys with the minor addition of Y2O3, Ti, and V were studied. The investigation focuses on the mechanical properties at high temperatures (up to 800 °C), resistance to so-called “475 °C embrittlement” (α and α’ phase separation), and irradiation resistance. The conducted tensile tests show promising mechanical properties at room temperature, i.e., the yield strength is 893±23 MPa, and the ultimate tensile strength is 993±10 MPa. The tensile tests at high temperatures also confirm good properties, e.g., at 600 °C the yield strength is 490±8 MPa, the ultimate tensile strength is 526±14 MPa, while the total elongation is 17±4 %. The results reveal that adding vanadium increases the strength of the FeCrAl ODS alloys. The conducted annealing at 475 °C for 1000 h shows limited hardening and almost no change in elongation of the alloy with the addition of vanadium. The performed ion irradiation experiments show good irradiation resistance of both tested alloys, manifesting by limited hardening and stable oxide precipitates. The results confirm the promising properties of studied materials for application in the nuclear industry, particularly in Generation IV reactors. Moreover, the results show the possibility of tuning properties by adding alloying elements, such as vanadium.
期刊介绍:
The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome.
The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example.
Topics covered by JNM
Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior.
Materials aspects of the entire fuel cycle.
Materials aspects of the actinides and their compounds.
Performance of nuclear waste materials; materials aspects of the immobilization of wastes.
Fusion reactor materials, including first walls, blankets, insulators and magnets.
Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties.
Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.