Korean Pyrochemical Process R&D activities

Abstract Korea is operating 20 nuclear units, producing about 700 t/yr of spent fuel. This spent fuel should be managed in a safe and practicable way. One option for this spent fuel management is treatment with pyrochemical process. Pyrochemical processflow sheetin KAERI includes voloxidation, electroreduction, electrorefining, electrowinning, and waste salt treatment processes. Each unit process has been tested in lab-scale, and these unit processes will be incorporated in PRIDE (PyRoprocess Inactive integrated DEmonstration) Facility in late 2011 in order to evaluate scaled-up design on the basis of the information of lab-scale experiments, integrity of each unit performance, and safeguards of integrated process, etc.

[1]  Do-Hee Ahn,et al.  Performance of the mesh-type liquid cadmium cathode structure for the electrodeposition of uranium from the molten salt , 2010 .

[2]  Robert Hill,et al.  Nonproliferation and safeguards aspects of the IFR , 1997 .

[3]  Jin-Mok Hur,et al.  An Electrochemical Reduction of Uranium Oxide in the Advanced Spent-Fuel Conditioning Process , 2008 .

[4]  Concentrations of CsCl and SrCl2 from a Simulated LiCl Salt Waste Generated by Pyroprocessing by Using Czochralski Method , 2009 .

[5]  Hansoo Lee,et al.  Salt evaporation behaviors of uranium deposits from an electrorefiner , 2010 .

[6]  Eung-Ho Kim,et al.  Application of Graphite as a Cathode Material for Electrorefining of Uranium , 2008 .

[7]  H. S. Lee,et al.  A study on the evaporation of cadmium for the recovery of actinides from a liquid cathode , 2010 .

[8]  Han-Soo Lee,et al.  Underpotential deposition of Li in a molten LiCl–Li2O electrolyte for the electrochemical reduction of U from uranium oxides , 2010 .

[9]  J. J. Laidler,et al.  Development of pyroprocessing technology , 1997 .

[10]  Hansoo Lee,et al.  Minimization of Eutectic Salt Waste from Pyroprocessing by Oxidative Precipitation of Lanthanides , 2009 .

[11]  Han-Soo Lee,et al.  Stabilization/solidification of radioactive salt waste by using xSiO2-yAl2O3-zP2O5 (SAP) material at molten salt state. , 2008, Environmental science & technology.

[12]  K. Ogawa,et al.  New Estimation Method for Void Reactivity Coefficient Using the TRACY Transient Data , 2009 .