Index Catalog // ScholarsArchive@OSU

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

The chemistry of acetohydroxamic acid related to nuclear fuel reprocessing

Creator:: Matteson, Brent Searle
Abstract:: Used Nuclear Fuel (UNF) contains transuranic (TRU) elements and numerous fission products as a result of the uranium fission process and neutron activation that occur in commercial light water power reactors. Recent environmental and nuclear proliferation concerns have spawned the development of advanced reprocessing techniques to close the nuclear fuel...
Resource Type:: Dissertation
Full Text:: Reprocessing Abstract approved: ________________________________________________ Alena Paulenova

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 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

Microstructure of radiation damage in the uranium film and its backing materials irradiated with 136 MeV 136Xe+26, Microstructure of radiation damage in the uranium film and its backing materials irradiated with 136 MeV ¹³⁶Xe⁺²⁶

Creator:: Sadi, Supriyadi
Abstract:: Microstructure changes in uranium and uranium/metal alloys due to radiation damage are of great interest in nuclear science and engineering. Titanium has attracted attention because of its similarity to Zr. It has been proposed for use in the second generation of fusion reactors due to its resistance to radiation-induced swelling....
Resource Type:: Dissertation
Full Text:: : ___________________________________________________________________ Alena Paulenova

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:: Nuclear Chemistry 280, 307–313 (2009). Lapka, J. L. & Paulenova, A. The Extraction of Actinides from

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

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

Investigation of f-Element Extraction and Ligand Association in the ALSEP Extraction System for Used Nuclear Fuel Reprocessing

Creator:: Holfeltz, Vanessa E.
Abstract:: Effective separation of lanthanides (Ln) from the minor actinides (MA) is a crucial technical challenge to closing the nuclear fuel cycle. This separation is a necessary prerequisite to transmute long-lived isotopes of Am and Cm, which will allow a reduction of the repository volume, thermal load, and radiological toxicity of...
Resource Type:: Dissertation
Full Text:: Used Nuclear Fuel Reprocessing. Abstract approved: Alena Paulenova Effective separation of

Organic Phase Inter-Ligand and Metal-Ligand Speciation in TALSPEAK and ALSEP Solvent Extraction Systems

Creator:: Gullekson, Brian J.
Abstract:: Partitioning of trivalent actinides (in particular, americium and curium) from the fission produced light lanthanides is a major concern of used nuclear fuel reprocessing for the purposes of waste disposal. Several solvent extraction processes have been developed to address these chemically difficult separations. The historically employed TALSPEAK Process utilizes di-2-ethylhexyl...
Resource Type:: Dissertation
Full Text:: Paulenova Partitioning of trivalent actinides (in particular, americium and curium) from the fission

ScholarsArchive@OSU

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

The chemistry of acetohydroxamic acid related to nuclear fuel reprocessing

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

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

Microstructure of radiation damage in the uranium film and its backing materials irradiated with 136 MeV 136Xe+26, Microstructure of radiation damage in the uranium film and its backing materials irradiated with 136 MeV ¹³⁶Xe⁺²⁶

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

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

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

Investigation of f-Element Extraction and Ligand Association in the ALSEP Extraction System for Used Nuclear Fuel Reprocessing

Organic Phase Inter-Ligand and Metal-Ligand Speciation in TALSPEAK and ALSEP Solvent Extraction Systems

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