Electrochemical study on the reduction mechanism of uranium-oxide in a LiCl-Li2O molten salt

Journal of Nuclear Science and Technology

Volumn 43, Issue 5, 2006, Pages 587-595

  Seo, Chung Seok ^a   Park, Sung Bin ^b   Park, Byung Heung ^b   Jung, Ki Jung ^b   Park, Seong Won ^b   Kim, Sung Hyun ^a  

^a Korea University   (South Korea)

^b Korea Atomic Energy Research Institute   (South Korea)

Author keywords

Electrolytic reduction; Mechanism; Molten salt; Uranium oxide; Voltammetry

Indexed keywords

MECHANISM; MOLTEN SALT; URANIUM OXIDE; VOLTAMMETRY;

CYCLIC VOLTAMMETRY; ELECTROLYSIS; LITHIUM COMPOUNDS; SALTS; URANIUM COMPOUNDS;

ELECTROLYTIC REDUCTION;

EID: 33745347474     PISSN: 00223131     EISSN: 00223131     Source Type: Journal    
DOI: 10.3327/jnst.43.587     Document Type: Article

References (17)

1. E. J. Karell, R. D. Pierce, T. P. Mulcahey, Treatment of Oxide Spent Nuclear Fuel Using the Lithium Reduction Process, Argonne National Laboratory Report, ANL/CMT/CP-89562, (1996).
2. M. Fujie, Y. Shoji, T. Kobayashi, "Development of Lithium Process for Reprocessing LWR Spent Fuel," Proc. GLOBAL '97: International Conference on Future Nuclear Systems, Yokohama, Japan, Oct. 5-10, 1997, p. 1448-1453 (1997).
3. 2 and Simulated Materials," Proc. GLOBAL '97: International Conference on Future Nuclear Systems, Yokohama, Japan, Oct. 5-10, 1997, p. 1472-1477 (1997).
4. J. J. Laidler, Treatment of Spent Oxide Fuel, Chemical Technology Division Annual Technical Report 1996, Argonne National Laboratory Report, p. 119-130, ANL-97/13 (1997).
5. J. J. Laidler, Pyrochemical Process Applications, Chemical Technology Division Annual Technical Report 1997, Argonne National Laboratory Report, p. 123-131, ANL-98/13 (1998).
6. T. Usami, T. Kato, M. Kurata, et al., "Lithium Reduction of Americium Dioxide to Generate Americium Metal," J. Nuclear Materials, 304, 50 (2002).
7. T. Usami, M. Kurata, T. Inoue, et al., "Pyrochemical Reduction of Uranium Dioxide and Plutonium Dioxide by Lithium Metal," J. Nuclear Materials, 300, 15 (2002).
8. S. D. Hermann, S. X. Li, M. F. Simpson, et al., "Electrolytic Reduction of Spent Oxide Fuel-Bench Scale Test Preparations," Proc. ANS Fifth Topical Meeting on DOE Spent Nuclear Fuel and Fissile Materials Management, Charleston, SC, Sept. 17-20, 2002 (2002).
9. M. A. Willamson, K. Gourishankar, L. Redey, et al., "Oxide Reduction to Convert Spent Fuel to Metal," Argonne National Laboratory Homepage, Chemical Engineering Division, Science & Technology, Nuclear Technology, Contacted in November, 2004.
10. K. Gourishankar, L. Reday, M. Williamson, "Electrochemical Reduction of Metal Oxides in Molten Salts, Light Metals," TMS, 1075 (2002).
11. 2O Systems," Proc. Global 2003, New Orleans, LA, Nov. 16-20, 2003 (2003).
12. R. K. Ahluwalia, H. K. Greyer, "The GC Computer code for Flow Sheet Simulation of Pyrochemical Processing of Spent Nuclear Fuels," Nucl. Tech., 116, 180 (1996).
13. F. Kobayashi, S. Kitawaki, Characterization of Ag/AgCl Reference Electrode in LiCl-KCl Eutectic Melt, Japan Atomic Energy Research Institute, JAERI-Tech 99-006 (2000).
14. T. Usami, M. Kurata, T. Inoue, "Pyrometallurgical Reduction of Unirradiated TRU Oxides by Lithim Chloride Medium," Proc. the Workshop on Pyrochemical Separations, Avignon, France, March 14-16, 2000, p. 165-175 (2000).
15. E. J. Karell, K. V. Gourishankar, "Separation of Actinides from LWR Spent Fuel Usiong Molten-Salt-Based Electro-chemical Process," Nucl. Tech., 136, 342 (2001).
16. T. M. Besmann, R. H. Cooper, "Chemical Thermodynamic Assessment of the Li-U-O system for Possible Space Nuclear Application," Oak Ridge National Laboratory, ORNL/ TM-9662 (1985).
17. 3" J. Inorg. Nucl. Chem., 36, 2291 (1974).