Preliminary evaluation of solvent-extraction and/or ion-exchange process for meeting AAA program multi-tier systems recovery and purification goals.

Pereira, C. ; Vandegrift, G. F. ; Swanson, J. L.

Argonne National Laboratory

关键词: Spent Fuels;    43 Particle Accelerators;    Rare Earths;    Purification;    11 Nuclear Fuel Cycle And Fuel Materials;   

DOI  :  10.2172/805261
RP-ID  :  ANL-02/29
RP-ID  :  W-31-109-ENG-38
RP-ID  :  805261

美国|英语

来源: UNT Digital Library

【 摘 要 】

Several potential processes are described and evaluated for their suitability in a multitier aqueous-based approach to processing dissolved spent nuclear fuel under the Advanced Accelerator Applications (AAA) program. The evaluation is focused on solvent extraction and ion exchange technologies that have been demonstrated to varying degrees. The goals of the program are to separate uranium (U), technetium (Tc), and the transuranic (TRU) elements from the fission products that are to be vitrified for disposal as high-level waste (HLW). Uranium will be disposed as low-level waste (LLW); Tc and TRU will be transmuted in an accelerator. A number of processes have been examined. The focus was on liquid-liquid solvent extraction processes because of their relatively high state of development and their suitability for high-throughput-rate processing. Ion exchange processes were also examined. PUREX and UREX were evaluated as options for recovery of uranium; UREX is also an option for Tc recovery. Solvent extraction options examined for TRU recovery included TRUEX, DIAMEX, and TRPO, as well as some based on TBP extraction. Processes for trivalent actinide separation from lanthanides were also examined. The PUREX processes have been developed over many years, and have been refined to a significant degree. In the first cycle, U and plutonium (Pu) are co-extracted from dissolved spent fuel solutions by TBP in a diluent, selectively stripped, and purified in additional extraction/strip cycles. Neptunium (Np) can be extracted or driven into the raffinate by adjusting the oxidation state. Trivalent actinides and fission products remain predominantly in the raffinate, although a significant Tc fraction will co-extract with the U and Pu.