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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Shameem Hasan, Tushar K. Ghosh, Mark A. Prelas, Dabir S. Viswanath, Veera M. Boddu
Nuclear Technology | Volume 159 | Number 1 | July 2007 | Pages 59-71
Technical Paper | Reprocessing | doi.org/10.13182/NT07-A3856
Articles are hosted by Taylor and Francis Online.
Chitosan was coated on an inert substrate, perlite, and was prepared as spherical beads for adsorption of uranium from aqueous solutions. The uptake capacity of chitosan-coated perlite beads for uranium varied from 98.9 to 149 000 g/g when the equilibrium concentration of uranium in the solution ranged from 11 ppb (11 g/l) to 1000 ppm (10 × 106 g/l) and the solution pH was 5. The adsorption capacity of chitosan-coated perlite beads for uranium decreased by 75% in the presence of 0.45 M NaCl, whereas the adsorption capacity decreased by 55% when TiO2 was added to the beads during their preparation. The adsorption capacity of TiO2-containing chitosan beads for uranium was found to be in the range of 2.5 to 40 g of uranium per gram of beads when the concentration of uranium was 39 to 734 g/l in the presence of 0.45 M NaCl. It was in the range of 18 to 302 g of uranium per gram of beads when the concentration was 990 to 47 000 g/l in the presence of 0.45 M Na2CO3. Chitosan-coated beads were found to preferentially adsorb uranium, Cd, and Cr from a mixture containing these ions along with Sr and Cs. Only a negligible amount of Sr and Cs was adsorbed by chitosan-coated beads. The data suggest that the chitosan-coated beads can be used for both extraction of uranium from waste streams and also from a highly acidic medium such as a reprocessing stream that uses nitric acid.
