Composition and Pressure Estimation on Salt Distillation Process after Electrorefining for Spent Nuclear Fuel

Yeon Ki Hong; Byung Heung Park

doi:10.4028/www.scientific.net/AMR.807-809.1277

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HomeAdvanced Materials ResearchAdvanced Materials Research Vols. 807-809Composition and Pressure Estimation on Salt...

Composition and Pressure Estimation on Salt Distillation Process after Electrorefining for Spent Nuclear Fuel

Abstract:

A pyroprocessing technology has been developed to process spent nuclear fuels with decreased waste and increased proliferation resistance. A main process of the pyroprocessing is an electrorefining which requires a post-treatment for recovered uranium. A distillation approach is adopted to remove an electrolyte salt residue on the uranium. In this work, the vapor composition of the distillation process and the total pressure were estimated to obtain basic data for process design and integration. Six chlorides including KCl, LiCl, UCl₃, PuCl₃, CeCl₃, and YCl₃ were considered to understand the behavior of the representative components of actinides and lanthanides. It was found that small amount of the actinides and lanthanides would be accompanied by the electrolyte salts (KCl and LiCl) during the distillation under high vacuum.

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Periodical:

Advanced Materials Research (Volumes 807-809)

Pages:

1277-1280

DOI:

https://doi.org/10.4028/www.scientific.net/AMR.807-809.1277

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Online since:

September 2013

Authors:

Yeon Ki Hong, Byung Heung Park

Keywords:

Distillation, Molten Salt, Phase Equilibria, Pyroprocessing, Spent Nuclear Fuel

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