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Irradiation creep of 3C–SiC and microstructural understanding of the underlying mechanisms
- Source :
- Journal of Nuclear Materials. 448:487-496
- Publication Year :
- 2014
- Publisher :
- Elsevier BV, 2014.
-
Abstract
- Irradiation-induced creep in high-purity silicon carbide was studied by an ion-irradiation method under various irradiation conditions. The tensioned surfaces of bent thin specimens were irradiated with 5.1 MeV Si 2+ ions up to 3 dpa at 280–1200 °C, which is referred to as a single-ion experiment. Additional He + ions were irradiated simultaneously in the dual-ion experiment to study the effects of transmuted helium on irradiation creep. Irradiation creep was observed above 400 °C in the single-ion case, where a linear relationship between irradiation creep and swelling (C/S) was observed at 400–800 °C for all stress levels (150, 225, and 300 MPa). The proportional constant of the C/S relationship was strongly dependent on temperature and stress. A rapid reduction in creep strain was observed above 1000 °C. On the basis of the microstructural analysis, anisotropic distribution of self-interstitial atom (SIA) clusters was suspected to be the primary creep mechanism. Some interesting results were obtained from re-irradiation under stress after the irradiation without stress. The creep strain was significantly retarded by pre-irradiation to even 0.01 dpa at 400 and 600 °C. This implies that the loop orientation was determined very early in the irradiation regime. For the dual-ion cases, irradiation creep was absent or very limited at all irradiation temperatures studied (400–800 °C). Microstructural analysis indicated that helium inhibited the stable growth of SIA clusters and prevented them from exhibiting anisotropic distribution.
- Subjects :
- Nuclear and High Energy Physics
Materials science
chemistry.chemical_element
Ion
Stress (mechanics)
chemistry.chemical_compound
Nuclear Energy and Engineering
chemistry
Creep
Silicon carbide
medicine
General Materials Science
Irradiation
Swelling
medicine.symptom
Composite material
Anisotropy
Helium
Subjects
Details
- ISSN :
- 00223115
- Volume :
- 448
- Database :
- OpenAIRE
- Journal :
- Journal of Nuclear Materials
- Accession number :
- edsair.doi...........25e0f3bcad34d39e93cdcc98eb2d058c
- Full Text :
- https://doi.org/10.1016/j.jnucmat.2013.09.004