Laser-induced breakdown spectroscopy for contamination analysis of Sr and Cs on 316L stainless steels in alkaline environment for spent nuclear fuel storage

The contamination of fission products (Sr-90 and Cs-137) on the metallic material (316L stainless steel) of alkaline spent fuel storage pond threatens to decommission nuclear facilities. Compared with previous studies unable to detect Cs on the surface of contaminated steel by laser-induced breakdown spectroscopy (LIBS), this study selected the emission lines of Sr II 407.74 nm and Cs I 455.77 nm as the analytical spectral lines of LIBS, and for the first time satisfactorily measured and analyzed the accumulation of Sr and Cs on the surface of 316L stainless steel for 7, 14, 21, 30 and 60 days, respectively. It was found during the accumulation, the concentration of Sr and Cs on the surface reached their maximum after 21 days, and relatively stabilized 30 days later. In addition, combined with the physicochemical characterizations, the contamination mechanism of Sr and Cs on 316L stainless steel was proposed, with the contaminants gradually diffusing from the oxide layer dissolved and damaged in the alkaline corrosive environment to the matrix. Strontium had two forms on the steel surface: SrCrO4 in the oxide layer and SrCO3 in the matrix, but the contamination of Cs was more inclined to the surface than Sr.

Automated summary

This study successfully measured and analyzed the accumulation of Sr and Cs on the surface of 316L stainless steel in the alkaline spent fuel storage pond using laser-induced breakdown spectroscopy. The concentration of Sr and Cs reached their maximum after 21 days and stabilized after 30 days. The contamination mechanism was proposed, with Sr in two forms on the steel surface, while Cs contamination was more inclined to the surface than Sr.