Advances in Development of the Fission Product Extraction Process for the Separation of Cesium and Strontium From Spent Nuclear Fuel

An Advanced TALSPEAK Concept for Separating Minor Actinides. Part 1. Process Optimization and Flowsheet Development

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An Advanced TALSPEAK Concept for Separating Minor Actinides. Part 2. Flowsheet Test with Actinide-spiked Simulant

Characterizing Diamylamylphosphonate (DAAP) as an Americium Ligand for Nuclear Fuel-Cycle Applications

Demonstration of the SREX Process for the Treatment of Actual High-Activity Tank Waste at the INEEL using Centrifugal Contractors

Demonstration of the TRUEX Process for the Treatment of Actual High-Activity Tank Waste at the INEEL Using Centrifugal Contractors

Development and demonstration of solvent extraction processes for the separation of radionuclides from acidic radioactive waste

article published in 1999

Development and evaluation of a silver mordenite composite sorbent for the partitioning of xenon from krypton in gas compositions

article

Development and testing of a cobalt dicarbollide based solvent extraction process for the separation of cesium and strontium from acidic tank waste

scholarly article by R. S. Herbst et al published 28 May 2002 in Separation Science and Technology

Development of Steam Reforming for the Solidification of the Cesium and Strontium Separations Product from Advanced Aqueous Reprocessing of Spent Nuclear Fuel

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Development of a Regenerable Strip Reagent for Treatment of Acidic, Radioactive Waste with Cobalt Dicarbollide‐based Solvent Extraction Processes

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Development of a hydrogen mordenite sorbent for the capture of krypton from used nuclear fuel reprocessing off-gas streams

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Development of a universal solvent for the decontamination of acidic liquid radioactive wastes

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Evaluation of the impacts of gamma radiolysis on an ALSEP process solvent

Extraction of Lanthanides with Diamides of Dipicolinic Acid from Nitric Acid Solutions. I

Extraction of Lanthanoids with Diamides of Dipcolinic Acid from Nitric Acid Solutions. II. Synergistic Effect of Ethyl-Tolyl Derivates and Dicarbollide Cobalt

scholarly article by A. Paulenova et al published March 2013 in Solvent Extraction and Ion Exchange

Extraction of molybdenum and technetium with diamides of dipicolinic acid from nitric acid solutions

Extraction of uranium(VI) with diamides of dipicolinic acid from nitric acid solutions

Fission Product Extraction (FPEX): Development of a Novel Solvent for the Simultaneous Separation of Strontium and Cesium from Acidic Solutions

Integrated AMP–PAN, TRUEX, and SREX testing. I. Extended flowsheet testing for separation of surrogate radionuclides from simulated acidic tank waste

Integrated AMP–PAN, TRUEX, and SREX testing. II. Flowsheet testing for separation of radionuclides from actual acidic radioactive waste

Microfluidic-Based Robotic Sampling System for Radioactive Solutions

Microfluidic-Based Sample Chips for Radioactive Solutions

Nuclear Fuel nuclear fuel , Reprocessing nuclear fuel reprocessing of

Oxidation and extraction of Am(VI) using a monoamidic extractant in 3D printed centrifugal contactors

Pilot-Scale TRUEX Flowsheet Testing for Separation of Actinides and Lanthanides from used Nuclear Fuel

Polyacrylonitrile-Chalcogel Hybrid Sorbents for Radioiodine Capture

scientific article published on 29 April 2014

Radiation stability of regenerated stripping solutions for high-level waste processing

Radioactive Iodine and Krypton Control for Nuclear Fuel Reprocessing Facilities

article

Radionuclide Extraction by 2,6‐Pyridinedicarboxylamide Derivatives and Chlorinated Cobalt Dicarbollide

scholarly article by V. N. Romanovskiy et al published June 2006 in Separation Science and Technology

Reprocessing of spent solvent of the UNEX process

Selective Extraction of Minor Actinides from Acidic Media Using Symmetric and Asymmetric Dithiophosphinic Acids

Separation of trivalent actinides from lanthanides in an acetate buffer solution using Cyanex 301

Synthesis of symmetric dithiophosphinic acids for “minor actinide” extraction

THE UNIVERSAL SOLVENT EXTRACTION (UNEX) PROCESS. I. DEVELOPMENT OF THE UNEX PROCESS SOLVENT FOR THE SEPARATION OF CESIUM, STRONTIUM, AND THE ACTINIDES FROM ACIDIC RADIOACTIVE WASTE

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THE UNIVERSAL SOLVENT EXTRACTION (UNEX) PROCESS. II. FLOWSHEET DEVELOPMENT AND DEMONSTRATION OF THE UNEX PROCESS FOR THE SEPARATION OF CESIUM, STRONTIUM, AND ACTINIDES FROM ACTUAL ACIDIC RADIOACTIVE WASTE

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The Radiolytic and Thermal Stability of Diamides of Dipicolinic Acid

The extraction of actinides from nitric acid solutions with diamides of dipicolinic acid

The solvent extraction of Am(VI) using centrifugal contactors

Thirty Stage Annular Centrifugal Contactor Thermal Profile Measurements

UNIVERSAL SOLVENT EXTRACTION (UNEX) FLOWSHEET TESTING FOR THE REMOVAL OF CESIUM, STRONTIUM, AND ACTINIDE ELEMENTS FROM RADIOACTIVE, ACIDIC DISSOLVED CALCINE WASTE

Use of Cyanex-301 for Separation of Am/Cm from Lanthanides in an Advanced Nuclear Fuel Cycle