Development, feasibility, and uncertainty of radioactive 22Na tracer dilution and gamma spectroscopy for mass determination of molten salt for pyroprocessing spent nuclear fuels

Article Nuclear Science & Technology

History and status of spent fuel treatment at the INL Fuel Conditioning Facility

Guy L. Fredrickson et al.

Summary: This paper provides a brief history of U.S. liquid metal cooled reactor development with emphasis on EBR-II, and a technical description of the electrometallurgical methods used for treating spent fuel and blanket materials.

PROGRESS IN NUCLEAR ENERGY (2022)

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Article Chemistry, Analytical

Gamma-ray spectra analyses of molten salts in spent nuclear fuels pyroprocessing facilities for mass measurement

Guoping Cao et al.

Summary: The study evaluated the use of radioactive tracer dilution and gamma spectroscopy in monitoring the mass of liquid salt in molten salt systems, focusing on the uncertainty analysis of Eu-154 isotope's gamma radioactivity. The research found that a longer data acquisition time and higher count rate gamma detector significantly improved the uncertainty of Eu-154 from 7% or 8% to 3%.

JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY (2022)

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Article Nuclear Science & Technology

Testing of an Element Tracer Dilution Method for Measurement of Total Mass of Molten Salt in a Nuclear Fuel Cycle Process or Molten Salt Reactor

Huan Zhang et al.

Summary: In this study, the total mass of molten salt in a nuclear system was measured using soluble tracers and elemental analysis. The experiment involved sequential additions of tracer salts and resulted in an average mass determination error of 2.39% for CeCl3 and 1.82% for KCl. The mass estimations were found to be mostly higher than the actual known mass.

NUCLEAR TECHNOLOGY (2022)

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Article Materials Science, Multidisciplinary

Voltammetry measurements in lithium chloride-lithium oxide (LiCl-Li2O) salt: An evaluation of working electrode materials

Ammon N. Williams et al.

Summary: This study evaluated several potential working electrode materials for monitoring the oxide reduction process, finding that 316L SS, Ir, and Pt performed well in the LiCl-Li2O electrolyte, with Ir being the most corrosion-resistant and Pt being the most sensitive to Li2O concentrations. It is recommended to use a CV probe fitted with Ir and Pt working electrodes for standalone safeguards instrumentation.

JOURNAL OF NUCLEAR MATERIALS (2021)

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Article Chemistry, Analytical