Phase Equilibria in Systems Relevant to Pyroprocessing
- 1. Argonne National Laboratory, 9700 S Cass Ave. Argonne, IL 60439 (United States)
- 2. Oregon State University, 1500 SW Jefferson St. Corvallis, OR 97331 (United States)
Description
Pyroprocessing has many advantages for the recovery and recycle of actinides, especially the transuranic elements, in used nuclear fuel. It has several unique features that distinguish it from other used fuel treatment technologies such as the ability to handle short-cooled fuel, a small process footprint, and production of metallic uranium and uranium - transuranic (U/TRU) products that can be directly fabricated into metallic fuel for advanced reactors. Recovery of the uranium and U/TRU products from the used fuel occurs in an electrorefining step. Uranium and transuranics in the used fuel (metal or reduced oxide) are dissolved at the anode in a molten chloride electrolyte, and electrodeposited at two different cathodes - one for uranium and another for the uranium - transuranic product. During this process, fission products less noble than uranium and transuranics (i.e., lanthanides, alkali and alkaline earth) anodically dissolve into the electrolyte, while only uranium and U/TRU are electrodeposited at the respective cathodes. Thus, there is a buildup of active metal and lanthanide fission products in the molten salt electrolyte. The goal of this work is to improve the fundamental understanding of the chemistry of actinides and transuranics in this complex, multicomponent solution. The fundamental thermodynamic properties of the multi-component molten salt electrolytes are complicated due to the formation of ternary and more complex compounds. As the actinides anodically dissolve at the anode and deposited at the cathode, a gradient in the concentration develops at the anode/electrolyte and the cathode/electrolyte interfaces. Ternary phase formation could impact the performance of the electrorefining system by influencing the chemical activity and thus the redox potentials of the actinide chlorides in the molten salt solution. Literature data on the LiCl-KCl-UCl3 system is limited, sometimes conflicting, and may reflect the use of older analytical instrumentation, which was less accurate than that currently available. In addition, there has not been any investigation of the low UCl3 concentration region of the system, which is the region relevant to electrorefining. (authors)
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 114
- Journal Issue
- 1
- Journal Page Range
- p. 211-212
- ISSN
- 0003-018X
Conference
- Title
- Annual Meeting of the American Nuclear Society
- Dates
- 12-16 Jun 2016
- Place
- New Orleans, LA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52032113
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ELECTRODEPOSITION; ELECTROREFINING; FISSION PRODUCTS; LITHIUM CHLORIDES; MATERIALS RECOVERY; MOLTEN SALTS; NUCLEAR FUELS; POTASSIUM CHLORIDES; RARE EARTHS; URANIUM; URANIUM CHLORIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; ALKALI METAL COMPOUNDS; CHLORIDES; CHLORINE COMPOUNDS; DEPOSITION; ELECTROLYSIS; ELEMENTS; ENERGY SOURCES; FUELS; HALIDES; HALOGEN COMPOUNDS; ISOTOPES; LITHIUM COMPOUNDS; LITHIUM HALIDES; LYSIS; MANAGEMENT; MATERIALS; METALS; POTASSIUM COMPOUNDS; POTASSIUM HALIDES; PROCESSING; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REFINING; SALTS; SURFACE COATING; URANIUM COMPOUNDS; URANIUM HALIDES; WASTE MANAGEMENT; WASTE PROCESSING
Optional Information
- Notes
- 2 refs.; Available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 United States