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Published on: October 19, 2017
Machine Learning Prediction of Nitric Acid Extraction Behavior in PUREX Process
Sankar V Harilal1,2, Matilda I Duffy1, Eva Brayfindley1
1Pacific Northwest National Laboratory, Richland, Washington 99352, United States.
Machine learning models accurately predict nitric acid behavior in Plutonium Uranium Reduction Extraction (PUREX) systems. This aids in optimizing experiments for nuclear fuel reprocessing and understanding actinide extraction.
Area of Science:
- Nuclear Chemistry
- Chemical Engineering
- Data Science
Background:
- The Plutonium Uranium Reduction Extraction (PUREX) process is vital for recovering plutonium and uranium from spent nuclear fuel.
- Predicting extraction parameters in PUREX is challenging due to complex aqueous feed compositions.
- Understanding nitric acid behavior is crucial as it influences actinide extraction in the PUREX process.
Purpose of the Study:
- To develop predictive models for nitric acid distribution in the PUREX system.
- To utilize machine learning to overcome limitations of traditional thermodynamic models.
- To provide an in silico tool for optimizing PUREX process design and experiments.
Main Methods:
- Compiled extensive solvent extraction literature data on nitric acid behavior.
- Developed machine learning models to predict organic phase nitric acid concentration.
- Investigated the influence of initial acid and tributyl phosphate concentrations and diluents.
Main Results:
- Machine learning models demonstrated high accuracy in predicting nitric acid equilibrium concentration.
- The models successfully correlated acid and TBP concentrations with nitric acid extraction across various diluents.
- Generated ML-aided response surfaces provide a novel predictive capability.
Conclusions:
- Machine learning offers a powerful approach for modeling complex chemical processes like PUREX.
- The developed ML models serve as a valuable in silico tool for PUREX process optimization.
- This work represents significant progress in predicting and optimizing actinide separation in nuclear fuel reprocessing.
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