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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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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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.”
O. K. Tallent, R. P. Wichner, Roy L. Towns
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 336-343
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33579
Articles are hosted by Taylor and Francis Online.
The transport or diffusion of uranium (as a stand-in for plutonium) was investigated under conditions approximating those of the primary coolant loop in a high-temperature gas-cooled reactor. Profiles were obtained for uranium penetration in H-451 graphite at temperatures ranging from 900 to 1400°C. Profile data for given temperatures were considered in terms of the following expression: where C is the concentration of uranium at time t, for distance x, into the pellet; C0 is a constant representing the uranium concentration at x = 0 for all t, and D is the diffusion coefficient. Diffusion coefficients for uranium initially present as dicarbide at 1000 and 1400°C were found to be defined byFor uranium initially present as dioxide at 900, 1000, and 1400°C, diffusion coefficients are defined bywhere R is the gas constant and T is the temperature in degrees Kelvin.