Continuous Ion Exchange for Uranium Recovery from Phosphoric Acid
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Solution Overview
Problem
Current methods for uranium recovery from wet-process phosphoric acid are inefficient and costly, lacking continuous contacting systems that could simplify the process and reduce operational issues associated with solvent extraction systems.
Innovation Solution
A dual or single cycle continuous ion exchange processing approach using ion exchange resins, such as LEWATIT® TP 260, AMBERLITE IRC-747, and PUROLITE S-930, to extract and purify uranium from phosphoric acid, reducing the need for extensive pretreatment and eliminating the use of solvent extractants.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Reliability
If solvent extraction methods are used for uranium recovery, then uranium can be recovered from phosphoric acid, but operational issues such as emulsion formation and solvent-related risks occur
Solution Approach 1:
The patent replaces solvent extraction (chemical/physical system) with ion exchange (solid-liquid contacting system). Specifically, it uses ion exchange resins in continuous columns to substitute the solvent extraction process, thereby eliminating emulsion formation and solvent-related operational risks while maintaining uranium recovery capability
Solution Approach 2:
The patent introduces ion exchange resin as an intermediary substance between phosphoric acid and uranium. The resin acts as a solid mediator that selectively binds uranium from the acid solution, replacing the traditional liquid solvent intermediary and avoiding the harmful effects associated with solvent extraction
2Reliability
If fixed bed ion exchange systems are used, then uranium recovery is effective from conventional sources, but the systems have limitations for phosphoric acid processing
Solution Approach 1:
The patent transitions from static fixed bed ion exchange systems to dynamic continuous ion exchange systems. The continuous system allows for ongoing processing of phosphoric acid through multiple stages including clarification, ion exchange, and regeneration, making the system adaptable and effective for phosphoric acid applications
Solution Approach 2:
The patent divides the ion exchange process into separate functional stages: clarification stage, ion exchange stage, and regeneration stage. This segmentation allows each stage to be optimized for its specific function, making the overall system adaptable to phosphoric acid processing requirements
3Reliability
If conventional recovery methods are used, then uranium can be recovered, but capital and operating costs are high
Solution Approach 1:
The patent implements continuous ion exchange processing where resin is continuously circulated between extraction and regeneration stages. This continuous operation eliminates downtime between batches, improves uranium recovery efficiency, and reduces capital and operating costs compared to conventional discontinuous methods
Solution Approach 2:
The patent recovers and reuses ion exchange resin through a regeneration process. After uranium extraction, the resin is regenerated in situ and returned to service, eliminating the need to discard and replace resin continuously. This recovery approach significantly reduces operational costs
Applied Scientific Principles
This section explains which scientific principles are used to turn an abstract innovation direction into a practical engineering solution.
Function Achieved in This Case
This method effectively recovers uranium with reduced capital and operating costs, simplifying the process and minimizing the need for extensive pretreatment, while avoiding issues like emulsion formation and solvent-related risks.
Implementation Method 1
a dual or single cycle continuous ion exchange processing approach using ion exchange resins, such as LEWATIT® TP 260, AMBERLITE IRC-747, and PUROLITE S-930, to extract and purify uranium from phosphoric acid
Data Source
AI summary
In alternative embodiments, the invention provides processes and methods for the recovery, removal or extracting of, and subsequent purification of uranium from a wet-process phosphoric acid using a continuous ion exchange processing approach, where the uranium is recovered from a phosphoric acid, or a phos-acid feedstock using either a dual or a single stage extraction methodology. In both cases an intermediate ammonium uranyl-tricarbonate solution is formed. In alternative embodiments, in the dual cycle approach, this solution is contacted in a second continuous ion exchange system with a strong anion exchange resin then subsequently recovered as an acidic uranyl solution that is further treated to produce an intermediate uranyl peroxide compound which is ultimately calcined to produce the final uranium oxide product. In alternative embodiments, in the single cycle case, the intermediate ammonium uranyl-tricarbonate solution is evaporated to decompose the ammonium carbonate and produce an intermediate uranium carbonate/oxide solid material. These solids are digested in an acid medium, and then processed in the same manner as the secondary regeneration solution from the dual cycle process to produce an intermediate uranyl peroxide that is calcined to produce a final uranium oxide product.