Understanding ion irradiation resistance of a silicon diffused nanostructured ferritic alloy-chromium carbide–carbon composite

Abstract

Cladding materials play the essential role in the safe, efficient, and economic operation of a nuclear reactor. In this work, a silicon diffused nanostructured ferritic alloy-chromium carbide–carbon (NFA|Si-Cr3C2-C) composite is studied as a nuclear fuel cladding material and ion irradiation with highly energetic Fe++ ions has been carried out to induce a peak damage level of ∼250 dpa. Elemental distribution, phase composition, and defect structure are investigated in order to understand the ion irradiation response of the NFA|Si-Cr3C2-C composite. SRIM simulation reveals displacement damage profiles for different phase compositions. The NFA|Si phase has good ion irradiation resistance with newly induced dislocation loops. The C phase in the NFA|Si matrix is prone to being partially amorphized whereas the Cr3C2 phase in the NFA|Si matrix is completely amorphized. This work offers important guidance for nuclear cladding material development.