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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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.”
John B. Case, Harris R. Greenberg, Bruce E. Kirstein
Nuclear Technology | Volume 207 | Number 1 | January 2021 | Pages 62-73
Technical Paper | doi.org/10.1080/00295450.2020.1747837
Articles are hosted by Taylor and Francis Online.
Analytical solutions for temperatures in an infinite region bounded internally by a cylinder have proved to be useful for thermal analysis of heat-producing nuclear waste disposal scenarios where the thermal design criteria are peak temperatures. The practicality of an analytical solution for the temperature of the host rock used in forced-ventilation thermal analyses has been illustrated by a computational time of a few seconds. Prior to the use of an analytical temperature solution for the host rock, the computation time was on the order of hours. However, the published analytical temperature solution for the infinite region bounded internally by a cylinder with constant heat flux applied at the cylinder wall does not satisfy the boundary condition. This temperature solution is shown to be correct herein with respect to temperature predictions derived from a solution that does satisfy the boundary condition.