| NUCLEAR PHYSICS |
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Microstructure and Mechanical Properties of Ti3SiC2 Irradiated by Carbon Ions |
| WANG Kun1,2, QI Qiang1,2, CHENG Gui-Jun1,2, SHI Li-Qun1,2** |
1Applied Ion Beam Physics Laboratory, Institute of Modern Physics, Fudan University, Shanghai 200433
2Department of Nuclear Science and Technology, Fudan University, Shanghai 200433
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| Cite this article: |
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WANG Kun, QI Qiang, CHENG Gui-Jun et al 2014 Chin. Phys. Lett. 31 072801 |
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Abstract Thanks to its noteworthy mechanical properties, excellent damage tolerance and good thermal stability, the Ti3SiC2 ternary compound has attracted great concern and has been considered as a potential structural component material for the 4th generation of reactors (e.g., gas fast nuclear reactors) and future fusion reactors. The outstanding properties are due to the nanolamellar structure which imparts characteristics of both metals and ceramics to this material. In our work, Ti3SiC2 samples have been irradiated by C+ ions with a high fluence of 1.78×1017 ions/cm2 at a range of temperatures from 120°C–850°C. Subsequently, series of characterization techniques including synchrotron irradiation x-ray diffraction, scanning electron microscopy and nano-indentation are carried out to understand the changes of microstructure and mechanical properties. The composition exhibits high damage tolerant properties and a high recovery rate through the analysis, especially at high temperature. The minimum damage to an irradiated sample appears around 350°C in the temperature range 120°C–550°C. At a high irradiation temperature, a significant reduction in the damage can be achieved and an almost complete lack of damage compared with an un-irradiated sample is revealed at the temperature of 850°C.
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Published: 30 June 2014
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| PACS: |
28.52.Fa
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(Materials)
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61.80.-x
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(Physical radiation effects, radiation damage)
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61.05.C-
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(X-ray diffraction and scattering)
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