journal article·2020-05Open access

In-beam creep of SiCf/SiC minicomposites under uniaxial tensile loading

Jiachao Chen, Sylvain Jacques, Marie-France Barthe, Chonghong Zhang, Pierre Desgardin

Abstract

Abstract A newly developed clamping system for ceramic specimen is described in the present report. By using this system, the uniaxial tensile loading was first successfully applied up to fracture (950 MPa) on a SiCf/SiC minicomposite. A minicomposite is a 1D model composite. It consists of a SiC-based fiber tow embedded in a SiC matrix, which has a diameter of about 0.5 mm. Afterwards, the irradiation creep properties of SiCf/SiC minicomposites were studied. In-situ creep was performed in an in-beam creep device under uniaxial tensile stresses from 40 to 382 MPa during homogeneous helium irradiation. Homogenous irradiation was carried out by helium implantation with energies varying from 0 to 45 MeV. The displacement dose rate was 1.2 × 10−6 dpa/s. The average temperature was controlled to 700 and 900 °C within ±15 °C. Irradiation creep compliance of minicomposite was measured to be 3.07 × 10−5 and 5.43 × 10−5 dpa−1 MPa−1 at 700 °C and 900 °C, respectively.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Advanced ceramic materials synthesis · Nuclear materials and radiation effects

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (30)

Show source-provided references
1. Silicon carbide composites as fusion power reactor structural materials10.1016/j.jnucmat.2011.03.005 ↗
2. Recent progress in the development of SiC composites for nuclear fusion applications10.1016/j.jnucmat.2018.06.017 ↗
3. SiC/SiC composites materials for nuclear application
4. Terrani, Accident tolerant fuel cladding development: promise, status, and Challenges10.1016/j.jnucmat.2017.12.043 ↗
5. ATF developments at PSI
6. 2002
7. Delayed failure of Hi-Nicalon and Hi-Nicalon S multifilament tows and single filaments at intermediate temperatures (500°–800°C)10.1111/j.1551-2916.2009.02924.x ↗
8. Properties of silicon carbide for nuclear fuel particle coatings10.13182/NT77-A31892 ↗
9. Light ion irradiation creep of SiC fibers in torsion10.1016/S0022-3115(98)00216-5 ↗
10. Irradiation creep of advanced silicon carbide fibers10.1016/S0022-3115(00)00264-6 ↗
11. Proton irradiation creep of beta-silicon carbide10.1016/j.jnucmat.2011.06.047 ↗
12. Tatsuya Hinoki, Observation and possible mechanism of irradiation induced creep in ceramics10.1016/j.jnucmat.2012.11.035 ↗
13. Irradiation creep of 3C–SiC and microstructural understanding of the underlying mechanisms10.1016/j.jnucmat.2013.09.004 ↗
14. Neutron-irradiation creep of silicon carbide materials beyond the initial transient10.1016/j.jnucmat.2016.06.006 ↗
15. micro/minicomposites: a useful approach to the design and development of non-oxide CMCs10.1016/S1359-835X(98)00147-X ↗
16. Cooling and temperature stabilizing of thin specimens for mechanical measurements under light ion bombardment10.1016/0029-554X(78)90400-7 ↗
17. An apparatus for applying tensile, compressive and cyclic stresses on foil specimen during light ion irradiation
18. Displacement damage in silicon carbide irradiated in fission reactors10.1016/j.jnucmat.2004.02.012 ↗
19. Ab initio molecular dynamics calculations of threshold displacement energies in silicon carbide
20. Total hemispherical emissivity of sintered SiC up to 1850 K in high vacuum and in air at different pressures10.1016/j.jeurceramsoc.2018.03.050 ↗
21. Irradiation creep and precipitation in a ferritic ODS steel under helium implantation10.1016/j.jnucmat.2007.04.051 ↗
22. Irradiation creep and microstructural changes of ODS steels of different Cr-contents during helium implantation under stress10.1016/j.jnucmat.2013.02.071 ↗
23. A transient irradiation creep in non-fissile metals10.1080/14786436308207296 ↗
24. Tensile creep behaviour of a silicon carbide fiber with a low oxygen content10.1007/BF00356326 ↗
25. Production and recovery of defects in SiC after irradiation and deformation10.1016/S0022-3115(98)00139-1 ↗
26. Radiation swelling of SiC under neutron irradiation
27. Dimensional changes of Al2O3 and SiC, proton irradiated under tensile stress10.1016/0022-3115(94)90999-7 ↗
28. Atomic displacement function of cubic metals10.1016/0022-3115(83)90011-9 ↗
29. Irradiation performance of cladding and structural steels in liquit metal reactors
30. Irradiation creep of candidate materials for advanced nuclear plants10.1016/j.jnucmat.2013.04.024 ↗