Silicon carbide(SiC)fiber possesses low neutron capture cross-section,low induced radioactivity,high thermal stability,low density,high specific strength,good oxidation-ablation resistance,high specific modulus,especially improved flaw tolerance and non-catastrophic mode of failure.Therefore,silicon carbide fiber is considered as a candidate structural component in advanced nuclear industry fields.The irradiation damage which silicon carbide fiber will experience cannot be ignored.In fission reactors,SiC fibers are inevitably subjected to irradiation by various fission fragments(heavy ions with up to hundreds of MeV)irradiation,which are produced via chain fission of the uranium.While in fusion reactors,the average energy of recoils produced by neutron irradiation in materials can reach several hundred keV.Most of the energy of fission fragments/recoils is deposited in the materials mainly through electronic processes(excitation and ionization of atoms along the trajectory of ions).Therefore,it is indispensable to acquire a comprehensive knowledge of the microstructure of SiC fibers under energetic-heavy-ion irradiation.
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