Rare earth removal from pyroprocessing fuel product for preparing MSR fuel
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A series of experiments were performed to produce a fuel source for a molten salt reactor (MSR) through pyroprocessing technology. A simulated LiCl–KCl–UCl3-NdCl3 salt system was prepared, and the U element was fully recovered using a liquid cadmium cathode (LCC) by applying a constant current. As a result, the salt was purified with an UCl3 concentration lower than 100 ppm. Subsequently, the U/RE ingot was prepared by melting U and RE metals in Y2O3 crucible at 1473 K as a surrogate for RE-rich ingot product from pyroprocessing. The produced ingot was sliced and used as a working electrode in LiCl–KCl–LaCl3 salt. Only RE elements were then anodically dissolved by applying potential at 1.7 V versus Ag/AgCl reference electrode. The RE-removed ingot product was used to produce UCl3 via the reaction with NH4Cl in a sealed reactor.
Abstract
A series of experiments were performed to produce a fuel source for a molten salt reactor (MSR) through pyroprocessing technology. A simulated LiCl–KCl–UCl3-NdCl3 salt system was prepared, and the U element was fully recovered using a liquid cadmium cathode (LCC) by applying a constant current. As a result, the salt was purified with an UCl3 concentration lower than 100 ppm. Subsequently, the U/RE ingot was prepared by melting U and RE metals in Y2O3 crucible at 1473 K as a surrogate for RE-rich ingot product from pyroprocessing. The produced ingot was sliced and used as a working electrode in LiCl–KCl–LaCl3 salt. Only RE elements were then anodically dissolved by applying potential at 1.7 V versus Ag/AgCl reference electrode. The RE-removed ingot product was used to produce UCl3 via the reaction with NH4Cl in a sealed reactor.
참고문헌 (19)
- O. Beneˇs, "Actinide burner fuel: potential compositions based on the thermodynamic evaluation of MF–PuF3 (M = Li, Na, K, Rb, Cs) and LaF3–PuF3systems", J. Nucl. Mater, 377, pp.449~457 (2008)
- Fast Spectrum Molten Salt Reactor Options, "D.E. Holcomb", ~, pp.ORNL (2011), TM-2011[DOI]
- A. Mourogov, "Potentialities of the fast spectrum molten salt reactor concept : REBUS-3700", Energy Convers. Manag, 47, pp.2761~2771 (2006)
- L.G. Alexander, "Molten-Salt Fast Reactors i", Proceedings of Breeding Large Fast Reactors (1963)
- M. Taube, "Molten plutonium chloride fast breeder reactor cooled by molten uranium chloride", Ann. Nucl. Sci. Eng, 1, pp.277~281 (1974)
- J. Serp, "The molten salt reactor(MSR)in generation IV : overview and perspectives", Prog. Nucl. Energy, 77, pp.308~319 (2014)
- B. Mignacca, "Economics and finance of molten salt reactors", Prog. Nucl. Energy, 129, pp.103503~ (2020)
- A. A. Kasam, "Conceptual Design of a Breed&burn Molten Salt Reactor", PhD, pp.2018
- J. P. Ackerman, "Chemical basis for pyrochemical reprocessing of nuclear fuel", Ind. Eng. Chem. Res, 30, pp.141~145 (1991)
- C.E. Till, "Plentiful Energy - the Story of the Integral Fast Reactor", 978-1466384606, ~ (2011)
- E. Choi, "Electrochemical processing of spent nuclear fuels : an overview of oxide reduction in pyroprocessing technology", Prog. Nat. Sci. : Mater. Int, 25, pp.572~582 (2015)
- J. P. Ackerman, "Distribution of plutonium, americium, and several rare earth fission product elements between liquid cadmium and LiC1-KC1 eutectic", J. Alloys Compd, 199, pp.77~84 (1993)
- M. Kurata, "Distribution behavior of uranium, neptunium, rare-earth elements (Y, La, Ce, Nd, Sm, Eu, Gd) and alkaline-earth metals (Sr,Ba) between molten LiC1-KC1eutectic salt and liquid cadmium or bismuth", J. Nucl. Mater, 227, pp.110~121 (1995)
- K. Kinoshita, "Separation of uranium and transuranic elements from rare earth elements by means of multistage extraction in LiCl-KCl", Bi system, 1999, pp.36, 189~197
- K. Kinoshita, "Countercurrent extraction test with continuous flow of molten LiCl-KCl salt and liquid Cd for pyro-reprocessing of metal FBR fuel", J. Nucl. Sci. Technol, 47, pp.211~218 (2010)
- O. Shirai, "Electrochemical behavior of actinides and actinide nitrides in LiCl-KCl eutectic melts", J. Alloys Compd, 408–412, pp.1267~1273 (2006)
- Y. Sakamura, "Measurement of standard potentials of actinides (U,Np,Pu,Am) in LiCl–KCl eutectic salt and separation of actinides from rare earths by electrorefining", J. Alloys Compd, 271–273, pp.592~586 (1998)
- D. Yoon, "Chlorination of uranium metal to uranium trichloride using ammonium chloride", J. Radioanal. Nucl. Chem, 331, pp.2209~2216 (2022)