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scott aase consulting, Radiochemical Processing, Nuclear Waste Treatment, Solvent Extraction Systems, System Engineering, Medical Isotope Production logo
Waste Treatment
Isotope Production
  • Method and apparatus for the extraction and processing of
    Mo-99

  • The Application of In Situ Formed Mixed Iron Oxides in the Removal of Strontium and Actinides from Nuclear Tank Waste

  • Development of a solvent extraction process for cesium removal from SRS tank waste.

  • Designing and Demonstration of the UREX+ Process Using Spent Nuclear Fuel

  • ANL progress in minimizing effects of LEU conversion on calcination of fission-product Mo-99 acid waste solution.

  • Hydraulic performance of a 5-cm CINC contactor for caustic-side solvent extraction.

  • Proof-of-Concept Flowsheet Tests for Cesium Removal from Tank Waste by Caustic-Side Solvent Extraction

  • Diogenic Transmutation Effects in a Crystalline Aluminosilicate Ceramic: a Tem Study

  • Experimental Verification of Caustic‐Side Solvent Extraction for Removal of Cesium from Tank Waste

  • Oxidation/reduction of multivalent actinides in the subsurface

  • EXAFS and XANES Analysis of Plutonium and Cerium Edges From Titanate Ceramics for Fissile Materials Disposal

  • Reduction of Np(VI) and Pu(VI) by organic chelating agents

  • Optimization of Magnetite Carrier Precipitation Process for Plutonium Waste Reduction

  • Actinide Separation of High-Level Waste Using Solvent Extractants on Magnetic Microparticles

  • Processing of LEU targets for Mo-99 production -- Dissolution of metal foils by nitric-acid/sulfuric-acid mixtures

  • Separation of isotopically enriched Yb-176 from Lu-177

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