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...
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...
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AlenaPaulenova
Industrial reprocessing of irradiated nuclear fuel (INF) is one of the
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...
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,...
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...
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...
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...
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...
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...
This thesis presents an approach to develop innovative methods for decontamination and surface protection applicable to naval nuclear ships and potentially, personnel, replacing antiquated techniques. To accomplish this goal, two products manufactured by CBI Polymers, LLC., DeconGel™ 1101 (1101) and a shampoo, DeconGel™ "prototype" (prototype), were tested.
The prototype was...