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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
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.”
Myunghwa Shim, Hongsuk Chung, Hiroshi Yoshida, Haksoo Jin, Min Ho Chang, Sei-Hun Yun, Seungyon Cho
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 856-860
Tritium Breeding | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-13
Articles are hosted by Taylor and Francis Online.
We are developing an innovative ZrCo hydride bed design, which is characterized by a large cylindrical filter, very thin cylindrical metal hydride powder packed layer, and large relative heating area per unit weight of ZrCo powder for ITER fuel cycle application. To validate this design concept, two ZrCo bed models each loaded with 127 g of ZrCo were tested by using H2 gas. In the first model, ZrCo powder was packed into the 3 mm gap between the filter cylinder and the vessel, and mold heater elements were attached to the outer surface of the vessel. The second model consisted of a layer of ZrCo powder packing (7 mm thickness), coiled cable heaters attached independently to the outer surface of the primary vessel and the inner surface of the filter cylinder. This paper presents detailed design features of the ZrCo bed models, and test results of the beds performances, i.e., temperature transient of the ZrCo packed bed during fast heating, hydriding rate up to 90-99% recovery, and 90-98% delivery fraction.