방사성폐기물학회지 (Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT))

  • 제20권2호
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  • Pages.209-229
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  • 2022
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  • 1738-1894(pISSN)
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  • 2288-5471(eISSN)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
권호 표지
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Review, Assessment, and Learning Lesson on How to Design a Spectroelectrochemical Experiment for the Molten Salt System

  • 투고 : 2022.04.21
  • 심사 : 2022.05.31
  • 발행 : 2022.06.30
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초록

This work provided a review of three techniques-(1) spectrochemical, (2) electrochemical, and (3) spectroelectrochemical-for molten salt medias. A spectroelectrochemical system was designed by utilizing this information. Here, we designed a spectroelectrochemical cell (SEC) and calibrated temperature controllers, and performed initial tests to explore the system's capability limit. There were several issues and a redesign of the cell was accomplished. The modification of the design allowed us to assemble, align the system with the light sources, and successfully transferred the setup inside a controlled environment. A preliminary run was executed to obtain transmission and absorption background of NaCl-CaCl2 salt at 600℃. It shows that the quartz cuvette has high transmittance effects across all wavelengths and there were lower transmittance effects at the lower wavelength in the molten salt media. Despite a successful initial run, the quartz vessel was mated to the inner cavity of the SEC body. Moreover, there was shearing in the patch cord which resulted in damage to the fiber optic cable, deterioration of the SEC, corrosion in the connection of the cell body, and fiber optic damage. The next generation of the SEC should attach a high temperature fiber optic patch cords without introducing internal mechanical stress to the patch cord body. In addition, MACOR should be used as the cell body materials to prevent corrosion of the surface and avoid the mating issue and a use of an adapter from a manufacturer that combines the free beam to a fiber optic cable should be incorporated in the future design.

키워드

과제정보

This work was conducted in conjunction with the Versatile Test Reactor project and is based upon work supported by U.S. Department of Energy under Prime Contract No. DE-AC07-05ID14517 to the Idaho National Laboratory. Any opinions, findings, and conclusions or recommendations expressed in this publication are preliminary and are those of the author(s) and do not necessarily reflect the views of the U.S. Department of Energy or the Idaho National Laboratory.

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