Nanocrystalline SiC and Ti3SiC2 Alloys for Reactor Materials: Diffusion of Fission Product Surrogates

Henager, Charles H.¹  Jiang, Weilin¹ 

[1]Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

关键词: Fission Products;    SiC;    MAX phases;    Ti3SiC2;    Fuel Cladding;    Environmental Molecular Sciences Laboratory;   

DOI  :  10.2172/1167315
RP-ID  :  PNNL--23881
PID  :  OSTI ID: 1167315
Others  :  Other: 44713
Others  :  NT0104000

学科分类：材料科学（综合）

美国|英语

来源: SciTech Connect

【 摘 要 】

MAX phases, such as titanium silicon carbide (Ti₃SiC₂), have a unique combination of both metallic and ceramic properties, which make them attractive for potential nuclear applications. Ti₃SiC₂ has been suggested in the literature as a possible fuel cladding material. Prior to the application, it is necessary to investigate diffusivities of fission products in the ternary compound at elevated temperatures. This study attempts to obtain relevant data and make an initial assessment for Ti₃SiC₂. Ion implantation was used to introduce fission product surrogates (Ag and Cs) and a noble metal (Au) in Ti₃SiC₂, SiC, and a dual-phase nanocomposite of Ti₃SiC₂/SiC synthesized at PNNL. Thermal annealing and in-situ Rutherford backscattering spectrometry (RBS) were employed to study the diffusivity of the various implanted species in the materials. In-situ RBS study of Ti₃SiC₂ implanted with Au ions at various temperatures was also performed. The experimental results indicate that the implanted Ag in SiC is immobile up to the highest temperature (1273 K) applied in this study; in contrast, significant out-diffusion of both Ag and Au in MAX phase Ti₃SiC₂ occurs during ion implantation at 873 K. Cs in Ti₃SiC₂ is found to diffuse during post-irradiation annealing at 973 K, and noticeable Cs release from the sample is observed. This study may suggest caution in using Ti₃SiC₂ as a fuel cladding material for advanced nuclear reactors operating at very high temperatures. Further studies of the related materials are recommended.