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Development of More Efficacious Tc-99m Organ Imaging Agents for Use in Nuclear Medicine by Analytical Characterization of Radiopharmaceutical Mixtures

Description: The long-range objective of this research program is the development of more efficacious technetium-99m radiopharmaceuticals for use as imaging agents in diagnostic nuclear medicine. We seek to isolate and develop distinct site imaging agents, each of which has properties optimized to provide diagnostic information concerning a given pathological condition. The specific objectives during the period (9/1/89 to 8/31/92) include: (1) Development of strategies for improving yields of specific Tc-di… more
Date: January 24, 1992
Creator: Heineman, W. R.
Partner: UNT Libraries Government Documents Department
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REACTIONS OF SOLVATED IONS. Final Report

Description: >Brief summaries are presented on isotopic dilution studies on salts dissolved in JCH/sub 3/OH, studies on metal and metal salts in solvents of the amine type, and studies on phosphato complexes of the pentammine Co(III) series. A list of papers published on reactions of solvated ions is included. (N.W.R.)
Date: September 24, 1962
Creator: Taube, H.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Technology Quarterly Progress Report, April-June 1962

Description: Aqueous zirconium fuel processing studies, directed at adapting the hydrofluoric acid process to continuous dissolution-complexing in order to increase the capacity of the ICPP process, resulted in determination of dissolution rates over a wide range of conditions. The addition of oxidants to 4.8M hydrofluoric acid used for the continuous dissolution of 3% uranium-Zircaloy- 2 fuel decreased the amount of uranium-containing residue in the dissolver at the expense of a decreased dissolution rate.… more
Date: September 24, 1962
Creator: Bower, J. R.
Partner: UNT Libraries Government Documents Department
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URANIUM RECOVERY FROM LAPRE-II FUEL SOLUTION BY TBP EXTRACTION

Description: A feed preparation and solvent extraction flowsheet was developed for the recovery and decontamination of highly enriched uranium from the LAPRE-II reactor fuel solution. The fuel solution, U(IV) in concentrated H/sub 3/PO/sup 4/ ' was dilutad, Fe(NO/sub 3/)/sub 3/ added to complex phosphate and supply salting strength, NaNO/sub 2/ added to oxidize U(IV) to U(VI) so that U may be extracted efficiently with 6% TBP. The flowsheet is designed for operation in noncritically safe equipment. (auth)
Date: June 24, 1960
Creator: Flanary, J R
Partner: UNT Libraries Government Documents Department
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{sup 31}P NMR study of the complexation of TBP with lanthanides and actinides in solution and in a clay matrix

Description: Goal was to use NMR to study TBP/lanthanide complexes in the interlayer or on edge sites of clays. Work in this laboratory yielded details of the complexation of Eu(NO{sub 3}){sub 3} and Pr(NO{sub 3}){sub 3} with TBP in hexane solution; this information is crucial to interpretation of results of NMR studies of the complexes exchanged into clays. The solution {sup 31}P-chemical shift values were improved by repeating the studies on the lanthanide salts dissolved directly into neat TBP. NMR studi… more
Date: July 24, 1994
Creator: Hartzell, C. J.
Partner: UNT Libraries Government Documents Department
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