Index Catalog // ScholarsArchive@OSU

Solvent Extraction Behavior of Mixed N, O-Donor Ligands for Separation of Trivalent f-Elements

Creator:: Karslyan, Yana
Abstract:: Nowadays selective separation processes are sought after more than ever before. They are indispensable to meet the growing demand for individual rare earth elements, minor actinides partitioned from fission-produced lanthanides, as well as, overall, more concentrated and high-purity products. This research focuses on such separation techniques as solvent extraction which...
Resource Type:: Dissertation
Full Text:: : _____________________________________________________ Alena Paulenova Nowadays selective separation processes are sought after more than ever

The effects of radiolysis and hydrolysis on the stability of extraction systems for minor actinides

Creator:: Wade, Emily C.
Abstract:: Industrial reprocessing of irradiated nuclear fuel (INF) is one of the most complex procedures performed on a large scale; the process is intricate due to the mix of radionuclides present in INF. As a global trend for nuclear power and reprocessing continues, research is geared toward optimizing the extraction of...
Resource Type:: Masters Thesis
Full Text:: : _____________________________________________________________________ Alena Paulenova Industrial reprocessing of irradiated nuclear fuel (INF) is one of the

Aqueous complexation of citric acid and DTPA with selected trivalent and tetravalent f-elements

Creator:: Brown, M. Alex
Abstract:: Carboxylic acids have played an important role in the field of actinide (An) and lanthanide (Ln) separations and the reprocessing of irradiated nuclear fuel. Recent bench-scale experiments have demonstrated that 3-carboxy-3-hydroxypentanedioic acid (citric acid) is a promising aqueous complexant that can effectively aid in the separation of transition metals from...
Resource Type:: Dissertation
Full Text:: Trivalent and Tetravalent f-Elements Abstract approved: Alena Paulenova Carboxylic acids

The investigation of dipicolinic acid diamide derivatives for the separation of actinides and lanthanides using solid phase extraction chromatography

Creator:: Black, Corrie D.
Abstract:: An alternative extractant for the TRUEX/UNEX process was investigated in solid phase extraction chromatography. The para and ortho isomers of diamides derivatives of dipicolinic acid (N,N'-diethyl-N,N'-ditolyl-dipicolinamide, EtTDPA) have been found in the past to effectively separate actinides from lanthanides in solvent extraction and were successfully impregnated on two uncoated, inert...
Resource Type:: Masters Thesis
Full Text:: my major advisor, Dr. Alena Paulenova for initially taking me as a student and pouring lots of time

The kinetic and radiolytic aspects of control of the redox speciation of neptunium in solutions of nitric acid

Creator:: Precek, Martin
Abstract:: Neptunium, with its rich redox chemistry, has a special position in the chemistry of actinides. With a decades-long history of development of aqueous separation methods for used nuclear fuel (UNF), management of neptunium remains an unresolved issue because of its not clearly defined redox speciation. Neptunium is present in two,...
Resource Type:: Dissertation
Full Text:: Alena Paulenova Neptunium, with its rich redox chemistry, has a special position in the chemistry

Investigations of two chemical systems relevant to pyroprocessing used nuclear fuel

Creator:: Hames, Amber
Abstract:: Pyroprocessing is an advanced technology for recycling used nuclear fuel. Pyrochemical processes encompass a wide range of chemical, physical, and electrochemical methods to partition fission products and other components from used nuclear fuel, which allows for the reuse of the actinides in nuclear fuel. This dissertation investigates two chemical systems...
Resource Type:: Dissertation
Full Text:: : ______________________________________________________ Alena Paulenova Pyroprocessing is an advanced technology for recycling used nuclear

Influence of temperature on the extraction of Pu(IV) by tri-n-butyl phosphate from acidic nitrate solutions

Creator:: Brown, M. Alex
Abstract:: The goal of Advanced Fuel Cycle Initiative program is to efficiently separate and recover actinides in attempts to reprocess irradiated nuclear fuel and reduce the necessary storage volume. In order to facilitate large-scale industrial applications of liquid-liquid separation processes, knowledge of the thermodynamic constants associated with the distribution of metal...
Resource Type:: Masters Thesis
Full Text:: (IV) by Tri-n-butyl Phosphate from Acidic Nitrate Solutions. Abstract approved: Alena

Removal of Radioactive Strontium, Iodine, and Uranium from Contaminated Groundwater : Sorption Processes and Properties

Creator:: Leonard, Mary E.
Abstract:: Iodine-129 is a key risk driver at sites where nuclear materials have been fabricated or processed, and it is a predominant isotope of concern in long-term waste storage strategies. I-129 exists primarily as iodate in the subsurface at the Hanford Site in south-central Washington State. Between 15 and 40% of...
Resource Type:: Dissertation
Full Text:: : ______________________________________________________________ Alena Paulenova Iodine-129 is a key risk driver at sites where nuclear materials have

Investigation of mixed N,O-donor dipicolinamide derivative ligands for use in nuclear fuel separations

Creator:: Lapka, Joseph
Abstract:: In this work, three isomeric forms of N, N'-diethyl, N, N'-ditolyldipicolinamide (EtTDPA) were synthesized. The elements thorium through americium, which make up a significant portion of the actinides in used nuclear fuel (with the exception of curium), and two fission products, molybdenum and technetium, were tested for their ability to...
Resource Type:: Dissertation
Full Text:: Abstract approved: ______________________________________________________ Alena Paulenova In

Process Optimization in the Chemical Life Cycle of Accelerator-Produced, Low Specific Activity 99Mo

Creator:: Bettinardi, David J.
Abstract:: Global efforts to support non-uranium approaches for 99Mo production, due to the proliferation risks associated with 235U fission-based production methods, have recently taken huge strides towards fruition. Several linear accelerator-based methods are currently in late-stage development that can produce low specific activity 99Mo from enriched 98/100Mo targets. The development of...
Resource Type:: Dissertation
Full Text:: : ______________________________________________________ Alena Paulenova Global efforts to support non-uranium approaches for 99Mo production

ScholarsArchive@OSU

Solvent Extraction Behavior of Mixed N, O-Donor Ligands for Separation of Trivalent f-Elements

The effects of radiolysis and hydrolysis on the stability of extraction systems for minor actinides

Aqueous complexation of citric acid and DTPA with selected trivalent and tetravalent f-elements

The investigation of dipicolinic acid diamide derivatives for the separation of actinides and lanthanides using solid phase extraction chromatography

The kinetic and radiolytic aspects of control of the redox speciation of neptunium in solutions of nitric acid

Investigations of two chemical systems relevant to pyroprocessing used nuclear fuel

Influence of temperature on the extraction of Pu(IV) by tri-n-butyl phosphate from acidic nitrate solutions

Removal of Radioactive Strontium, Iodine, and Uranium from Contaminated Groundwater : Sorption Processes and Properties

Investigation of mixed N,O-donor dipicolinamide derivative ligands for use in nuclear fuel separations

Process Optimization in the Chemical Life Cycle of Accelerator-Produced, Low Specific Activity 99Mo

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