Oral Presentation International Solvent Extraction Conference 2025

A Case Study of Fundamental Chemistry Advancing Through Full-Scale Deployment: What General Lessons Emerge? (122589)

Bruce A Moyer 1
  1. Oak Ridge National Laboratory, Oak Ridge, TN, United States

The use of a calixarene-crown ether in the removal of cesium from alkaline nitrate nuclear waste is a satisfying tale of fundamental chemistry advancing through applied research and development, scale-up, and deployment at full scale.1,2 A 30+ year odyssey, this endeavor—still in the making toward treating 34 million gallons of nuclear waste at the Savannah River Site in the USA—teaches hard lessons in adapting laboratory chemistry to the rigors of real-world application. Here is a recitation of some of the many questions encountered and lessons learned in bringing one solvent extraction (SX) process to fruition.

 

Chemistry

 

  • How much selectivity do we need?
  • How do we effect an extraction-stripping cycle?
  • Chemists are told they can choose any diluent “as long as it’s kerosene.” Thankfully, we can sneak in a modifier.
  • Solvent components must be designed for high stability and washing-out of inevitable degradation products.
  • Super-efficient stripping is needed but hard to achieve for high decontamination factors.

 

Flowsheet and engineering

 

  • High extraction selectivity pays dividends, but thank goodness for scrubbing.
  • Chemistry must adapt to engineering equipment. Having good distribution performance is just the start.
  • How robust to feed variations does a process need to be?
  • How good are simulants in predicting performance?
  • A strong temperature effect can be both good and bad.

 

Plant and system

 

  • SX is just one unit operation in the system. It must accept feed from upstream operations with minimal adjustments and deliver an ideal product effluent for downstream processing with minimal adjustments.
  • Throughput is often limited by other operations in the plant.
  • Filtration upstream of SX is evil but necessary.
  • What is this stuff (aka CRUD)? Where did it come from?
  • SX gets a bad rap, because it’s not “green.” The good news is that organic losses can be reduced to <10 ppm with passive equipment.

 

General lessons

 

  • Generation of knowledge continues even through plant operation, long after the first journal articles were published. Fundamental chemistry must stay engaged.
  • SX doesn’t have to be the most economical of alternative separation technologies to be selected for deployment.
  • Don’t count on sustained research funding over the long haul, especially in crossing the “valley of death.”

 

Every application is unique in the challenges that must be overcome. The Caustic-Side Solvent Extraction process (CSSX)1 and the Next-Generation CSSX process (NG-CSSX)2 were designed to remove cesium from alkaline waste containing 5–7 M sodium salts generated from decades of reprocessing spent nuclear fuel for weapons production. Approximately 34 Mgal (130,000 m3) such Cold War waste was produced at the Savannah River Site in the USA through the 1980s. Cesium-137 constitutes the primary soluble radionuclide in the waste and must by regulations be removed with a decontamination factor (DF) of >40,000 (i.e., >99.9975% removal).3 Calixarene-crown-6 ethers reported by European researchers provide the needed extraordinary separation factors of >10,000 for Cs vs Na.4 These molecules possess an elegant aromatic pocket of the perfect size for Cs+ ion, but they cannot function without a diluent modifier, as they have poor solubility and weak extraction strength by themselves in aliphatic diluents. Making them function adequately required designing an alcohol modifier with a fluorinated substituent to boost its hydrogen-bond-donor ability.5 The structure of the modifier had to be crafted to avoid third-phase formation, to resist hydrolytic degradation, and to yield degradation products that could be washed out. Together, the extractant-modifier combination proved robust to variations in waste composition.6 For the process to provide a DF of >40,000 means that stripping must be as efficient as extraction, which proved to be a perplexing problem.7,8 A strong exothermic temperature dependence was exploited for efficient stripping at elevated temperature. An organic base called a “suppressor” was included as an important stripping aid. Scrubbing was found to be essential to remove co-extracted impurities and adjust the solvent for stripping.6 The resulting expensive solvents exhibit good performance in centrifugal contactors and can also be recovered using passive coalescers on the raffinate and strip-effluent streams.9 Upstream filtration has limited throughput overall, and problems with deposits in the contactors and coalescers continue to require intervention.10,11 Despite the experience with such problems, the CSSX process and the powerful Next-Generation CSSX process deliver 15-fold or better concentrated streams of nearly pure cesium salt for vitrification.

  1. Moyer, B. A.; Birdwell, J. F., Jr.; Bonnesen, P. V.; Delmau, L. H. Use of Macrocycles in Nuclear-Waste Cleanup: A Real-World Application of a Calixcrown in Technology for the Separation of Cesium. In Macrocyclic Chemistry—Current Trends and Future, Gloe, K. Ed.; Springer, 2005; pp 383–405. DOI: 10.1007/1-4020-3687-6_24
  2. Bessen, N. P.; Moyer, B. A. An Advanced Solvent for the Caustic-Side Solvent Extraction of Cesium from Nuclear Waste: Comparing Lipophilic Guanidines for Improved Hydrolytic Stability. Solvent Extr. Ion Exch. 2024, 42 (5), 394–414. DOI: 10.1080/07366299.2024.2392511.
  3. Crouse, S. H.; Prasad, R.; Maharjan, N.; Ocampo, V. C.; Woodham, W. H.; Lambert, D.; Rousseau, R. W.; Grover, M. A. Selected Chemical Engineering Applications in Nuclear-Waste Processing at the Savannah River Site. Annu. Rev. Chem. Biomol. Eng. 2025, 16, 5.1–5.22. DOI: 10.1146/annurev-chembioeng-082223-053509.
  4. Dozol, J.-F.; Rainer, L. Extraction of Radioactive Elements by Calixarenes. In Ion Exchange and Solvent Extraction, Moyer, B. A. Ed.; Vol. 19; Taylor and Francis, 2010; pp 195–318.
  5. Bonnesen, P. V.; Delmau, L. H.; Moyer, B. A.; Lumetta, G. J. Development of Effective Solvent modifiers for the Solvent Extraction of Cesium from Alkaline High-Level Tank Waste. Solvent Extr. Ion Exch. 2003, 21 (2), 141–170. DOI: DOI: 10.1081/SEI-120018944.
  6. Williams, N. J.; Roach, B. D.; Lentsch, R. D.; Moyer, B. A. An Application of Molecular Recognition for the Efficient Removal of Cesium from Hanford Nuclear Waste by Modular Solvent Extraction. Solvent Extr. Ion Exch. 2025, Submitted.
  7. Delmau, L. H.; Bazelaire, E.; Bonnesen, P. V.; Engle, N. L.; Gorbunova, M. G.; Haverlock, T. J.; Moyer, B. A.; Ensor, D. D.; Meadors, V. M.; Harmon, B. W.; Bartsch, R. A.; Surowiec, M. A.; Zhou, H. Dramatic Improvements in Caustic-Side Solvent Extraction of Cesium Through More Efficient Stripping. In International Solvent Extraction Conference ISEC 2008, Tucson, AZ, 2008; Moyer, B. A., Ed.; Metallurgical Society of CIM: Vol. 1. DOI: 10.1016/S0304-386X(03)00120-8.
  8. Delmau, L. H.; Bonnesen, P. V.; Moyer, B. A. A Solution to Stripping Problems Caused by Organophilic Anion impurities in Crown-Ether-Based Solvent Extraction Systems: A Case Study of Cesium Removal from Radioactive Wastes. Hydrometallurgy 2004, 72 (1–2), 9–19. DOI: 10.1016/S0304-386X(03)00120-8.
  9. Lentsch, R. D.; Stephens, A. B.; Bartling, K. E.; Singer, S. A. Caustic-Side Solvent Extraction Full-Scale Test - 8431. In Proc. Waste Management 2008 (WM2008), Feb. 24–28, 2008, Phoenix, AZ; Waste Management Symposia: Tempe, AZ, 2008; Paper 8431. https://archivedproceedings.econference.io/wmsym/2008/pdfs/8431.pdf
  10. Clark, M.; DesRocher, N.; Lentsch, R. Operational Enhancements at the Salt Waste Processing Facility - 24541. In Waste Management 2024 (WM2024), Phoenix, AZ; Paper 24541, 2024. https://www.osti.gov/servlets/purl/2323547
  11. Conner, C.; Hogg, R.; Schulte, J.; Seagraves, T.; Burns, T.; Lentsch, R. Savannah River Site Liquid Waste Optimizations – 23353. In Proc. Waste Management 2023 (WM2023), Feb. 26–Mar. 2, 2023, Phoenix, AZ; Waste Management Symposia: Tempe, AZ, 2023; Paper 23353, 2023. https://s3.amazonaws.com/amz.xcdsystem.com/A464D2CF-E476-F46B-841E415B85C431CC_abstract_File803/FinalPaper_23353_0226121406.pdf
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