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Sharma, Kumari K

Publications and source records attributed to Sharma, Kumari K.

Spent-fuel recycling molecule degradation product standards can be produced with preparative liquid chromatography

Solvent systems used for spent nuclear fuel separation schemes are subject to intense radiation fields from the spent fuel, resulting in a degradation of separation performance over time from both the radiolytic destruction of active compounds (extractants, holdback agents, etc.) and the production of degradation compounds (compounds produced from the destruction of the active compounds). Development of a quantitative understanding of the effects of radiolysis on separations is impeded by a near-complete lack of availability of degradation products from chemical manufacturers. Synthesis of these degradation products through traditional means is both cost and time prohibitive, inhibiting advancement of new fuel separation processes. We hypothesize that comprehensive sets of degradation products can be synthesized using preparative radiolysis, and purified using high performance liquid chromatography in quantities sufficient for unequivocal identification and subsequent use as quantitative analytical studies. Achieving this objective will facilitate development of a much more accurate understanding of radiolysis reactions and their effects on solvent extraction processes, positioning Idaho National Laboratory (INL) in a leadership role in the science of fuel cycle separations. We propose producing these degradation compounds by irradiating concentrated samples of solvent ligands in the INL gamma irradiator, separating the resulting mixture with preparative chromatography, and removing the mobile phase in the separated fractions with a vacuum concentrator. This will yield milligram to gram quantities of purified degradation products, sufficient for fundamental research, at a fraction of the time and cost of synthesis. Facile production of separation molecule degradation products at minimal cost will enable the fundamental research that will accelerate the development of fuel cycles that will ensure the competitiveness of nuclear energy.

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Task-Specific Ionic Compounds for In-Field Sample Preparation Poster

In the event of a nuclear detonation, actinide and fission product-containing debris can be analyzed to provide information about the nature of the device. In-field sample dissolution prior to transport to a laboratory is critical for reducing the time between an event and delivery of information to decision makers. However, the best dissolution methods utilize liquid strong acid solutions, which are incompatible with field collection Standard Operating Procedure. What is required are solid materials that, when mixed with water in the field, can provide the strong digestion and dissolution properties of nitric and hydrofluoric acids. Fluorohydrogenate ionic liquids have shown a remarkable ability to dissolve a wide range of materials, from refractory actinide oxides to cementitious material such as calcium silicates. These strong dissolution properties are due to the neutral hydrofluoric acid that is bound to the anion component of the ionic liquid. Because these materials are liquids, they are also incompatible with Standard Operating Procedure. However, the physiochemical properties of ionic liquids, such as the melting point, can be readily tuned through minor modification of the molecular structure of the cations and anions. Thus, we hypothesize that by synthesizing modified cations, novel ionic compounds with melting points above ambient but with the same anion and bound hydrofluoric acid – and thus similar digestion and dissolution properties – as current fluorohydrogenate ionic liquids can be produced. These solid materials would be compatible with current Standard Operating Procedure, and would allow for rapid, in-field dissolution of samples, shortening the time to actionable information after an event.

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