Abstract
To evaluate radioactive tracer dilution and gamma spectroscopy as a safeguards technique for monitoring the mass of liquid salt in molten salt systems, the gamma spectroscopy data of salt samples from the pyroprocessing facilities in Idaho National Laboratory were acquired and analyzed. The primary focus is the uncertainty analysis of the gamma radioactivity of 154Eu isotope in the molten salts. The facilities include an electrorefiner for pyroprocessing spent oxide fuels (SOF-ER) and Mark-IV ER for processing the metallic fuels from Experimental Breeder Reactor-II (EBR-II). The relative gamma radioactivity uncertainty was consistently at 3% for 137Cs for both Mark-IV ER and SOF-ER salts. However, for 154Eu, it was 8% for SOF-ER salt and 7% for Mark-IV ER salt. The main reason for the higher uncertainty for 154Eu is believed to be the lower counting statistics in gamma spectroscopy. To improve the gamma radioactivity uncertainty of isotope 154Eu, a longer data acquisition time (12 h instead of 4 h) and a higher count rate gamma detector for gamma spectroscopy were tested and it was found that the uncertainty for 154Eu was significantly improved from 7% or 8–3%.
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Acknowledgements
This work was supported by the U.S. Department of Energy (DOE), Office of Nuclear Energy, under DOE Idaho Operations Office contract number DE-AC07-05ID14517. Accordingly, the U.S. Government retains and the publisher, by accepting the article for publication, acknowledges that the U.S. Government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript or allow others to do so, for U.S. Government purposes.
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Cao, G., Larson, N., Storms, B. et al. Gamma-ray spectra analyses of molten salts in spent nuclear fuels pyroprocessing facilities for mass measurement. J Radioanal Nucl Chem 331, 3085–3091 (2022). https://doi.org/10.1007/s10967-022-08339-5
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DOI: https://doi.org/10.1007/s10967-022-08339-5