Feasibility studies of using N,N-dihexyloctanamide (DHOA) for fast reactor fuel reprocessing applications
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Jammu Ravi
,
C. Mallika
Abstract
N,N-dihexyloctanamide (DHOA) is being considered as a promising extractant in the aqueous reprocessing of spent nuclear fuels. In view of rise in temperature of the solvent during reprocessing of fast reactor fuel, the present study aimed at evaluating the physical properties such as density, viscosity, and interfacial tension and Pu(IV) extraction behavior in 1.1 M DHOA/n-dodecane as a function of temperature and duration of heating. The influence of nitric acid in altering the physical properties with respect to temperature was evaluated. Physical properties and extraction behavior of the solvent changed to a remarkable extent with temperature. Quantitative amount of Pu(IV) could be back-extracted from loaded, solvent in three contacts at 313 K. FT-IR studies were carried out to evaluate the thermal stability of the solvent. Thus, the performance of the solvent, 1.1 M DHOA/n-dodecane is satisfactory at higher temperatures also.
Acknowledgment
Authors would like to thank Dr. K.A. Venkatesan of chemistry group, IGCAR for helping in carrying out Pu(IV) extraction studies and for having fruitful discussions.
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©2018 Walter de Gruyter GmbH, Berlin/Boston
Articles in the same Issue
- Frontmatter
- Redox behavior and solubility of plutonium under alkaline, reducing conditions
- Effects of temperature on the extraction of U(VI) and Pu(IV) by tris(2-methylbutyl) phosphate from nitric acid media
- Interaction of salicylic acid with zirconium diphosphate and its reactivity toward uranium (VI)
- Complexation of a macrocyclic ligand, 2,6-di (N-methyl)formamide-calix[4]pyridine, with Eu(III) and extraction of Eu(III) and Am(III)
- Feasibility studies of using N,N-dihexyloctanamide (DHOA) for fast reactor fuel reprocessing applications
- Encapsulated polymeric beads impregnating unexplored amide, N,N′-bis(2-ethyl hexyl) α-hydroxy acetamide (BEHGA) – preparation, sorption and kinetic studies for tri-, tetra- and hexavalent radionuclides
- Radioiodination of olmesartan medoxomil and biological evaluation of the product as a tracer for cardiac imaging
- Investigation of chemical composition and moisture content for different materials on the attenuation of γ rays
Articles in the same Issue
- Frontmatter
- Redox behavior and solubility of plutonium under alkaline, reducing conditions
- Effects of temperature on the extraction of U(VI) and Pu(IV) by tris(2-methylbutyl) phosphate from nitric acid media
- Interaction of salicylic acid with zirconium diphosphate and its reactivity toward uranium (VI)
- Complexation of a macrocyclic ligand, 2,6-di (N-methyl)formamide-calix[4]pyridine, with Eu(III) and extraction of Eu(III) and Am(III)
- Feasibility studies of using N,N-dihexyloctanamide (DHOA) for fast reactor fuel reprocessing applications
- Encapsulated polymeric beads impregnating unexplored amide, N,N′-bis(2-ethyl hexyl) α-hydroxy acetamide (BEHGA) – preparation, sorption and kinetic studies for tri-, tetra- and hexavalent radionuclides
- Radioiodination of olmesartan medoxomil and biological evaluation of the product as a tracer for cardiac imaging
- Investigation of chemical composition and moisture content for different materials on the attenuation of γ rays
