Review

  • Journal of Nuclear Fuel Cycle and Waste Technology
  • Volume 10(4); 2012
  • Article

Journal of Nuclear Fuel Cycle and Waste Technology 2012;10(4):273-280. Published online: Dec, 30, 2012

Studies on the Electrochemical Dissolution for the Treatment of 10 g-Scale Zircaloy-4 Cladding Hull Wastes in LiCl-KCl Molten Salts

  • You Lee Lee ; Chang Hwa Lee ; Min Ku Jeon ; Kweon Ho Kang
Abstract

The electrochemical behaviors of 10 g-scale fresh and oxidized Zircaloy-4 cladding hulls were examined in 500oC LiCl-KCl molten salts to confirm the feasibility of the electrorefining process for the treatment of hull wastes. In the results of measuring the potential-current response using a stainless steel basket filled with oxidized Zircaloy-4 hull specimens, the oxidation peak of Zr appears to be at -0.7 to -0.8 V vs. Ag/AgCl, which is similar to that of fresh Zircaloy-4 hulls, while the oxidation current is found to be much smaller than that of fresh Zircaloy-4 hulls. These results are congruent with the outcome of current-time curves at -0.78 V and of measuring the change in the average weight and thickness after the electrochemical dissolution process. Although the oxide layer on the surface affects the uniformity and rate of dissolution by decreasing the conductivity of Zircaloy-4 hulls, electrochemical dissolution is considered to occur owing to the defect of the surface and phase properties of the Zr oxide layer.

Keywords

Zircaloy-4,Hull wastes,Molten salts,Zr oxide,Dissolution,Electrorefining